From 811db85be3a09dd258bd0a5ee76773e9e3d6bd36 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 18:39:26 +0200 Subject: [PATCH 01/22] new structure for chapter 3 --- chapters/chapter3/monoblocks.tex | 18 ++- chapters/demo_monoblock.tex | 212 +++++++++++++++++++++++++++++++ main.tex | 1 + 3 files changed, 221 insertions(+), 10 deletions(-) create mode 100644 chapters/demo_monoblock.tex diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index f1617b7..f309ed3 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -12,21 +12,19 @@ \section{Introduction} A parametric study will then be performed to link the monoblock H inventory to the exposure conditions. Finally, the influence of edge effects (desorption on poloidal and toroidal gaps) will be highlighted. -\section{Interface conditions} -\input{chapters/chapter3/monoblocks/interface_conditions} -% \section{Influence of cycling} +\section{Simulation assumptions} +\subsection{Influence of dimension} +\subsection{Influence of cycling} +\subsection{Influence of interface condition} +\input{chapters/chapter3/monoblocks/interface_conditions} -% \begin{itemize} -% \item Redo one or two sims in Etienne paper ? -% \item continuous first to load the monoblock then cycling -% \end{itemize} +\section{Monoblock behaviour law} \label{influence of exposure conditions} -\section{Exposure conditions} \label{influence of exposure conditions} \input{chapters/chapter3/monoblocks/parametric_study} -\section{Edge effects} \label{3D edge effects} \labsec{3D edge effects} -\input{chapters/chapter3/monoblocks/3D_monoblocks} +% \section{Edge effects} \label{3D edge effects} \labsec{3D edge effects} +% \input{chapters/chapter3/monoblocks/3D_monoblocks} \section{Summary} H transport in ITER-like monoblocks was simulated with FESTIM. diff --git a/chapters/demo_monoblock.tex b/chapters/demo_monoblock.tex new file mode 100644 index 0000000..e47d2c3 --- /dev/null +++ b/chapters/demo_monoblock.tex @@ -0,0 +1,212 @@ +So far, only 2D monoblocks simulations were run, assuming an infinite thickness (or assuming no desorption from the poloidal gaps). +The goal of this section is to assess the influence of 3D edge effects on the monoblocks simulation results. +It will be shown that the error induced by 2D assumption decreases for thick monoblocks. + +\subsection{Methodology} + +The DEMO monoblock geometry differs slightly from the ITER geometry (see Figure \ref{fig: geometry DEMO monoblock}) but the general concept is the same, meaning the observations made in this Section are also valid for the ITER geometry. + + +\begin{figure} + \centering + \begin{overpic}[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/sketch.pdf} + \put(21, 15){\SI{23}{mm}} + \put(51, 50){\SI{25}{mm}} + % \put(21, 15){\SI{13.5}{mm}} + \put(21, 56){ \diameter \SI{12}{mm}} + \put(21, 63){ \diameter \SI{15}{mm}} + \put(21, 68){ \diameter \SI{17}{mm}} + \put(10, 70){\large$\Gamma_\mathrm{top}$} + \put(0, 60){\large$\Gamma_\mathrm{toroidal}$} + \put(43, 60){\large$\Gamma_\mathrm{toroidal}$} + \put(21, 45){\large$\Gamma_\mathrm{coolant}$} + \put(68, 71){e} + \put(66, 50){e + \SI{1}{mm}} + \put(60, 60){\large$\Gamma_\mathrm{poloidal}$} + \put(75, 60){\large$\Gamma_\mathrm{poloidal}$} + \end{overpic} + \caption{3D geometry of the DEMO monoblock used for the simulations showing W armour \cruleme[grey]{0.3cm}{0.3cm}, Cu interlayer \cruleme[orange]{0.3cm}{0.3cm}, CuCrZr alloy cooling pipe \cruleme[yellow]{0.3cm}{0.3cm}.} + \label{fig: geometry DEMO monoblock} +\end{figure} + +The boundary conditions for the steady state heat transfer problem are the same as for the 2D case (see Equation \ref{eq: bc thermal DEMO monoblock}). +The boundary conditions for the transient H transport problem are similar (see Equations \ref{eq: bc H transport DEMO monoblock}). +A non-homogeneous mobile concentration is assumed at the plasma exposed surface to simulate an implanted source of particles (see Section \ref{triangle model}). +Depending on the simulation case (with or without desorption on the gaps), the other external surfaces (except the cooling surfaces) will either be insulated or an instantaneous recombination will be assumed. + + +\begin{subequations} + \begin{align} + -\lambda \vec{\nabla} T \cdot \vec{n} &=\varphi_\mathrm{heat} \quad &\text { on } \Gamma_\mathrm{top}\\ + -\lambda \vec{\nabla} T\cdot \vec{n} &= -h \cdot \left(T_\mathrm{coolant} - T\right)\quad &\text { on } \Gamma_\mathrm{coolant} + \end{align} + \label{eq: bc thermal DEMO monoblock} +\end{subequations} +where $\varphi_\mathrm{heat}=\SI{10}{MW}$, $h=\SI{7e4}{W.m^{-2}.K^{-1}}$ is the heat exchange coefficient and $T_\mathrm{coolant} = \SI{323}{K}$ is the coolant temperature. + +\begin{subequations} + \begin{align} + c_\mathrm{m} &= \frac{\varphi_\mathrm{imp} R_p}{D} \quad &\text { on } \Gamma_\mathrm{top}\\ + -D \vec{\nabla} c_\mathrm{m} \cdot \vec{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ + c_\mathrm{m} &= 0 \quad &\text { on } \Gamma_\mathrm{toroidal} \text{ and } \Gamma_\mathrm{pipe} \\ + c_\mathrm{m} &= 0 \quad \text{or} \quad -D \vec{\nabla} c_\mathrm{m} \cdot \vec{n} = 0 &\text { on } \Gamma_\mathrm{poloidal} + \end{align} + \label{eq: bc H transport DEMO monoblock} +\end{subequations} +where $\varphi_\mathrm{imp} = \SI{1.6e22}{H.m^{-2}.s^{-1}}$ is the implanted particle flux, $R_p = \SI{1e-9}{m}$ is the particle implantation depth, $K_\mathrm{CuCrZr}=2.9\times 10^{-14}\exp{-1.92/(k_B T)}$ is the H recombination coefficient in CuCrZr expressed in \si{m^4.s^{-1}}. + +Two intrinsic traps were set in W, one trap in the Cu interlayer and two traps in the CuCrZr cooling pipe (see Table \ref{tab:traps monoblock DEMO}). + +\begin{table*} + \centering + \begin{tabular}{L{1.5cm} L{1.5cm} R{1.6cm} R{1.1cm} R{1.6cm} R{1.1cm} R{2cm}} + & Material & $k_0 (\si{m^3.s^{-1}})$ & $E_k (\si{eV})$ & $p_0 (\si{s^{-1}})$ & $E_p (\si{eV})$ & $n_i (\si{at.fr.})$ \\ + \hline + \\ + Trap 1 & W & $8.96 \times 10^{-17}$ & 0.39 & $1 \times 10^{13}$& 0.87 & $1.0 \times 10^{-3}$ \\ + \\ + Trap 2 & W & $8.96 \times 10^{-17}$ & 0.39 & $1 \times 10^{13}$& 1.00 & $4.0 \times 10^{-4}$ \\ + \\ + Trap 3 & Cu & $6.0 \times 10^{-17}$ & 0.39 & $8.0 \times 10^{13}$ & 0.50 &$5.0 \times 10^{-5}$\\ + \\ + Trap 4 & CuCrZr & $1.2\times 10^{-16}$ & 0.42 & $8.0 \times 10^{13}$ & 0.85 &$5.0 \times 10^{-5}$\\ + \\ + % Trap 5 & CuCrZr & $1.2\times 10^{-16}$ & 0.42 & $8.0 \times 10^{13}$ & 0.83 &$4.0 \times 10^{-2}$\\ + % \\ + \end{tabular} + \caption{Traps properties used in the 3D DEMO monoblocks simulations.} + \label{tab:traps monoblock DEMO} +\end{table*} + +Transient simulations up to \SI{e7}{s} were run. + +\subsection{Standard case} + +FESTIM simulations were run with and without desorption on the gaps. + +% Temperature field + +The temperature field obtained was very similar to the 2D case (see Figure \ref{fig: T field 3D monoblock}) with a top surface temperature of approximately \SI{1200}{K}. + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/temperature_3D_monoblock.png} + \caption{Temperature field of the 3D DEMO monoblock.} + \label{fig: T field 3D monoblock} +\end{figure} + + +% Retention fields +As expected, a higher retention was observed in the case without desorption (see Figure \ref{fig:retention fields 3D monoblocks}). +This is explained by the surface losses. +% The maximum retention for the case with desorption is three orders of magnitude lower than that of the case without desorption. +% In both cases, the higher retention was found to be in the CuCrZr cooling pipe. +% This is consistent with the obsverations made previously. + +\begin{figure} [h] + \centering + \begin{subfigure}{0.45\linewidth} + \centering + \includegraphics[trim=500 0 300 0, clip, width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/retention_1e3s.png} + \caption{$t=\SI{1e3}{s}$} + \end{subfigure}% + \qquad + \begin{subfigure}{0.45\linewidth} + \centering + \includegraphics[trim=500 0 300 0, clip, width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/retention_1e4s.png} + \caption{$t=\SI{1e4}{s}$} + \end{subfigure} + \begin{subfigure}{0.45\linewidth} + \centering + \includegraphics[trim=500 0 300 0, clip, width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/retention_1e5s.png} + \caption{$t=\SI{1e5}{s}$} + \end{subfigure}% + \qquad + \begin{subfigure}{0.45\linewidth} + \centering + \includegraphics[trim=500 0 300 0, clip, width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/retention_1e6s.png} + \caption{$t=\SI{1e6}{s}$} + \end{subfigure} + \caption{Retention fields of the DEMO monoblock with (left) or without (right) recombination on the poloidal gaps (standard case). Note the colour bars are different.} + \label{fig:retention fields 3D monoblocks} +\end{figure} + +% Inventory +The total H inventory in the monoblock was also between one and three orders of magnitude lower in the case with desorption (see Figure \ref{fig: inventory vs time DEMO monoblock}). +This difference increased with the exposure time. +Moreover, the steady state was reached way earlier for the case with desorption whereas the inventory kept increasing after \SI{e7}{s} for the insulated case. +This means that not taking desorption from the gaps into account in 2D simulations is a conservative assumption in terms of H inventory. +The simulations performed in Section \ref{influence of exposure conditions} then overestimate the monoblock H inventory. + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/inventory_standard_case_w_wo_recomb.pdf} + \caption{Temporal evolution of the monoblock inventory (standard case).} + \label{fig: inventory vs time DEMO monoblock} +\end{figure} + +% fluxes +These 3D simulations are however essential to estimate the outgassing fluxes from the poloidal gaps. +The particle flux at the poloidal gap is six times higher than the flux at the toroidal gap (see Figure \ref{fig: fluxes DEMO monoblock}). +The permeation flux to the coolant is five to six orders orders of magnitude lower than the fluxes at the gaps. +The particle fluxes at the gaps (poloidal and toroidal) were approximately \SI{e12}{H.s^{-1}} whereas the flux towards the cooling channel was below \SI{e7}{H.s^{-1}}. +The values of the outgassing fluxes from both the gaps are orders of magnitude lower than that of the retrodesorbed flux (\textit{ie} the flux of implanted particles that diffuse back to the exposed surface). +This means 3D edge effects will not affect previous results regarding the outgassing to the vessel. +They will however impact the value of the contamination flux towards the coolant as assuming an instantaneous recombination on the gaps will lead to way less particles reaching the cooling surface and therefore a lower flux. + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/desorption_flux_standard_case.pdf} + \caption{Temporal evolution of outgassing fluxes for the standard case with desorption from the poloidal gaps. Blue lines correspond to the fluxes towards the vacuum vessel, the orange line is the flux towards the coolant.} + \label{fig: fluxes DEMO monoblock} +\end{figure} + +\subsection{Influence of the monoblock thickness} + +Several simulations were run with monoblock thicknesses varying from \SI{4}{mm} to \SI{14}{mm}. + +% inventory +As the thickness increases, the inventory per unit thickness increases for the case with instantaneous recombination on the poloidal gap (see Figure \ref{fig: inventory vs time DEMO monoblock}). +It remains constant for the case with no recombination since it is equivalent to a 2D case (the decrease observed at low thicknesses is due to the impact of the CuCrZr pipe between monoblocks as shown on Figure \ref{fig: geometry DEMO monoblock}). +The relative difference between the cases with or without recombination on the poloidal gap decreases as the thickness increases. +After \SI{1e6}{s} of exposure, for a thickness of \SI{4}{mm} the relative difference is \SI{200}{\%} and drops at \SI{30}{\%} for \SI{14}{mm}. +This result was expected as the edge effects become negligible at large thicknesses. + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/inventory_vs_thickness.pdf} + \caption{Evolution of the inventory with or without recombination at the poloidal gap for several monoblock thicknesses at $t=\SI{1e6}{s}$} + \label{fig: ratio 3D thickness monoblock} +\end{figure} + +% flux +The permeation flux towards the cooling channel per unit thickness globally increases with the monoblock thickness (see Figure \ref{fig: flux to coolant DEMO monoblock}). +It is always higher in the case without recombination on the gaps. +Similarly to the inventory, the relative difference between the cases with or without recombination on the poloidal gap decreases with the thickness. + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/permeation_flux_vs_thickness.pdf} + \caption{Evolution of the permeation flux to the coolant with or without recombination at the poloidal gap for several monoblock thicknesses at $t=\SI{1e6}{s}$.} + \label{fig: flux to coolant DEMO monoblock} +\end{figure} + +% impact of the extrusion +Finally, the extrusion of the CuCrZr pipe between monoblocks has an impact on the permeation flux and the inventory. +Without this extrusion, the case without recombination on the poloidal gap corresponds to a pure 2D case and the inventory is independent of the thickness (see Figure \ref{fig: inventory monoblock vs thickness no gap}). + +\begin{figure} [h] + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/inventory_vs_thickness_no_gap.pdf} + \caption{Evolution of the permeation flux with or without recombination at the poloidal gap for several monoblock thicknesses without CuCrZr extrusion at $t=\SI{1e6}{s}$.} + \label{fig: inventory monoblock vs thickness no gap} +\end{figure} + +\subsection{Summary} +The influence of H desorption on poloidal and toroidal gaps between monoblocks was investigated. +The DEMO baseline geometry (based on an ITER-like concept) was simulated with FESTIM. +It was shown that taking into account recombination on these gaps could drastically decrease the monoblock H inventory (by several orders of magnitude). +In other words, this makes the 2D assumption for monoblocks less valid for (1) thin monoblocks (2) long exposure times. +Indeed, a 2D assumption implies assuming an infinitely thick monoblock (which is totally unrealistic for the ITER and DEMO designs). +However, this assumption is conservative since it will overestimate the H inventory and the permeation flux to the coolant. +Moreover, performing 3D simulations is more computationaly expensive than 2D simulations. diff --git a/main.tex b/main.tex index 713fdd7..c8b59b7 100644 --- a/main.tex +++ b/main.tex @@ -269,6 +269,7 @@ \input{chapters/v_and_v} \input{chapters/interface_transient.tex} +\input{chapters/demo_monoblock.tex} % \input{chapters/appendix.tex} % \input{chapters/breeding_blankets} % \input{chapters/codeposition_model} From 083e340e3ecd024765202b2298c79437746d77ee Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 19:26:56 +0200 Subject: [PATCH 02/22] moved things around + updated materials properties + added figures --- .../comparison_inventory_1d_2d_3d.pdf | Bin 0 -> 11929 bytes .../comparison_inventory_cycling.pdf | Bin 0 -> 17267 bytes .../monoblocks/dimension_approximation.png | Bin 0 -> 384330 bytes chapters/chapter3/monoblocks.tex | 148 +++++++++- .../monoblocks/interface_conditions.tex | 272 +----------------- .../chapter3/monoblocks/parametric_study.tex | 16 -- 6 files changed, 146 insertions(+), 290 deletions(-) create mode 100644 Figures/Chapter3/monoblocks/3D_monoblocks/comparison_inventory_1d_2d_3d.pdf create 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conditions. Finally, the influence of edge effects (desorption on poloidal and toroidal gaps) will be highlighted. +\section{Model description} -\section{Simulation assumptions} +\begin{figure} + \begin{overpic}[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/monoblock_sketch.pdf} + \put(42, 5){\SI{28}{mm}} + \put(97, 50){\SI{28}{mm}} + \put(10, 32){\SI{13.5}{mm}} + \put(42, 62){ \diameter \SI{12}{mm}} + \put(42, 71){ \diameter \SI{15}{mm}} + \put(42, 76){ \diameter \SI{17}{mm}} + \put(20, 80){\large$\Gamma_\mathrm{top}$} + \put(4, 60){\large$\Gamma_\mathrm{toroidal}$} + \put(78, 60){\large$\Gamma_\mathrm{toroidal}$} + \put(40, 41){\large$\Gamma_\mathrm{coolant}$} + \end{overpic} + \caption{ITER monoblock geometry showing W armour \cruleme[grey]{0.3cm}{0.3cm}, Cu interlayer \cruleme[orange]{0.3cm}{0.3cm}, CuCrZr alloy cooling pipe \cruleme[yellow]{0.3cm}{0.3cm}. The monoblock thickness is \SI{12}{mm}.}\label{fig: monoblock geometry} + \label{fig: monoblock 2d geometry} +\end{figure} + +\begin{subequations} + \begin{align} + -\lambda \vec{\nabla} T \cdot \vec{n} &=\varphi_\mathrm{heat} \quad &\text { on } \Gamma_\mathrm{top}\\ + -\lambda \vec{\nabla} T\cdot \vec{n} &= -h \cdot \left(T_\mathrm{coolant} - T\right)\quad &\text { on } \Gamma_\mathrm{coolant} + \end{align} + \label{eq: bc thermal monoblock} +\end{subequations} + +\begin{subequations} + \begin{align} + c_\mathrm{m} &= \frac{\varphi_\mathrm{imp} R_p}{D} \quad &\text { on } \Gamma_\mathrm{top}\\ + -D \vec{\nabla} c_\mathrm{m} \cdot \vec{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ + c_\mathrm{m} &= 0 \quad &\text { on } \Gamma_\mathrm{toroidal} \text{ and } \Gamma_\mathrm{poloidal} \\ + \end{align} + \label{eq: bc H transport monoblock} +\end{subequations} + +\begin{table*} + \centering + \begin{tabular}{p{1.7cm} R{3cm} R{3cm} R{1.8cm} R{1cm} R{1.8cm} R{1cm}} + & \multicolumn{2}{c}{Thermal properties} & \multicolumn{4}{c}{Hydrogen transport properties}\\ + \hline + Material & $\rho \cdot C_p \newline(\si{J.K^{-1}.m^{-3}})$ & $\lambda \newline(\si{W.m^{-1}.K^{-1}})$ & $D_0 \newline(\si{m^2.s^{-1}})$ & $E_\mathrm{diff} \newline(\si{eV})$ & $S_0 \newline(\si{m^{-3}.Pa^{-0.5}})$ & $E_\mathrm{S} \newline(\si{eV})$\\ + \hline + \\ + W \cite{frauenfelder_solution_1969,fernandez_hydrogen_2015}& % + $5.1\times 10^{-6} \cdot T^3 \newline - 8.3\times 10^{-2}\cdot T^2 \newline + 6.0 \times 10^{2}\cdot T \newline +2.4\times 10^6$ &% + $-7.8\times 10^{-9}\cdot T^3 \newline % + +5.0\times 10^{-5}\cdot T^2 \newline% + -1.1\times 10^{-1} \cdot T \newline% + +1.8\times 10^{2}$ &% + $1.9\times 10^{-7}$ & 0.20 &% + $1.87\times 10^{24}$ & 1.04\\ + \\ + Cu \cite{reiter_compilation_1996}&% + $1.7\times 10^{-4}\cdot T^3\newline % + +6.1\times 10^{-2}\cdot T^2\newline % + +4.7\times 10^2\cdot T\newline % + +3.5\times 10^6$ &% + + $-3.9\times 10^{-8}\cdot T^3\newline % + +3.8\times 10^{-5}\cdot T^2\newline % + -7.9\times 10^{-2}\cdot T\newline % + +4.0\times 10^2 $&% + + $6.6\times 10^{-7}$ &% + 0.39&% + $3.14\times 10^{24}$ & 0.57\\ + \\ + CuCrZr \cite{serra_hydrogen_1998}& % + $-1.8\times 10^{-4}\cdot T^3 \newline % + +1.5\times 10^{-1}\cdot T^2\newline % + +6.2\times 10^2\cdot T\newline % + +3.5\times 10^6$ &% + + $5.3\times 10^{-7}\cdot T^3\newline % + -6.5\times 10^{-4}\cdot T^2\newline % + +2.6\times 10^{-1}\cdot T\newline % + +3.1\times 10^2$ & % + + $3.9\times 10^{-7}$ & % + 0.42&% + $4.28\times 10^{23}$ & 0.39\\ + \\ + \\ + \end{tabular} + \caption{Materials properties used in the simulations. Thermal properties are fitted from ANSYS.} + \label{tab:materials properties monoblock} +\end{table*} + +\begin{figure} + \centering + \begin{subfigure}{\linewidth} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/thermal_prop.pdf} + \caption{Thermal properties} + \end{subfigure} + \begin{subfigure}{\linewidth} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/H_properties.pdf} + \caption{H transport properties} + \end{subfigure} + \caption{Material properties used in the simulations \cite{frauenfelder_solution_1969, reiter_compilation_1996, serra_hydrogen_1998, aiello_hydrogen_2002}} + \label{fig:properties monoblock} +\end{figure} + +\begin{table*} + \centering + \begin{tabular}{L{1.5cm} L{1.5cm} R{1.7cm} R{1.1cm} R{1.6cm} R{1.1cm} R{1.9cm}} + & Material & $k_0 (\si{m^3.s^{-1}})$ & $E_k (\si{eV})$ & $p_0 (\si{s^{-1}})$ & $E_p (\si{eV})$ & $n_i (\si{at.fr.})$ \\ + \hline + \\ + Trap 1 & W & $8.96 \times 10^{-17}$ & 0.2 & $1 \times 10^{13}$& 0.87 & $1.1 \times 10^{-3}$ \\ + \\ + Trap 2 & W & $8.96 \times 10^{-17}$ & 0.2 & $1 \times 10^{13}$& 1.00 & $4.0 \times 10^{-4}$ \\ + \\ + Trap 3 & Cu & $6.0 \times 10^{-17}$ & 0.39 & $8.0 \times 10^{13}$ & 0.50 &$5.0 \times 10^{-5}$\\ + \\ + Trap 4 & CuCrZr & $1.2\times 10^{-16}$ & 0.42 & $8.0 \times 10^{13}$ & 0.85 &$5.0 \times 10^{-5}$\\ + \\ + \end{tabular} + \caption{Traps properties used in the simulations \cite{hodille_macroscopic_2015, dolan_assessment_1994}} + \label{tab:traps monoblock} +\end{table*} + +\section{Simulation simplifications} \subsection{Influence of dimension} -\subsection{Influence of cycling} +\begin{figure} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/dimension_approximation.png} + \caption{} +\end{figure} + +\begin{figure} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/comparison_inventory_1d_2d_3d.pdf} + \caption{} +\end{figure} + \subsection{Influence of interface condition} \input{chapters/chapter3/monoblocks/interface_conditions} +\subsection{Influence of cycling} +\begin{figure} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/comparison_inventory_cycling.pdf} + \caption{} +\end{figure} + \section{Monoblock behaviour law} \label{influence of exposure conditions} \input{chapters/chapter3/monoblocks/parametric_study} -% \section{Edge effects} \label{3D edge effects} \labsec{3D edge effects} -% \input{chapters/chapter3/monoblocks/3D_monoblocks} - \section{Summary} H transport in ITER-like monoblocks was simulated with FESTIM. Several aspects of the simulations were studied. diff --git a/chapters/chapter3/monoblocks/interface_conditions.tex b/chapters/chapter3/monoblocks/interface_conditions.tex index 2349a0e..fbd8d59 100644 --- a/chapters/chapter3/monoblocks/interface_conditions.tex +++ b/chapters/chapter3/monoblocks/interface_conditions.tex @@ -4,275 +4,7 @@ The materials properties used for the simulations can be found in Table \ref{tab:materials properties_1}. In both cases the solute concentration $c_\mathrm{m}$ was set to \SI{1e20}{m^{-3}} at $x=0$ and zero on the other boundary. -% The governing equations for the diffusion problem with conservation of chemical potential read: -% \begin{subequations} -% \begin{align} -% \frac{\partial c_\mathrm{m}}{\partial t} &=\nabla \cdot\left(D(T) \nabla c_\mathrm{m}\right) \\ -% D^- \nabla c_\mathrm{m}^- &= D^+ \nabla c_\mathrm{m}^+ \\ -% \left(\frac{c_\mathrm{m}}{S}\right)^- &= \left(\frac{c_\mathrm{m}}{S}\right)^+ -% \end{align} -% \end{subequations} -% where $c_\mathrm{m}$ is the concentration of mobile H in \si{m^{-3}}, $D$ is the diffusion coefficient in \si{m^2.s^{-1}}, $S$ is the solubility of H in the material in \si{m^{-3}.Pa^{-0.5}}. -% The exponents $+$ and $-$ denote the two sides of the interface between the two subdomains. - -% not necessary... -% \subsection{W/Cu case} -% A \SI{4}{mm}-thick slab made of \SI{2}{mm} of W (referred as $\Omega_1$) and \SI{2}{mm} of Cu (referred as $\Omega_2$) at $T=\SI{500}{K}$ was first simulated. - - -% \begin{figure*} -% \centering -% \subfloat[Solute profiles at steady state (W/Cu)]{% -% \label{fig: solute profiles w cu} -% \begin{overpic}[width=0.5\linewidth]{Figures/Chapter3/monoblocks/interface_condition/w_cu/solute_profiles.pdf} -% \put(35, 55){W} -% \put(65, 35){Cu} -% \end{overpic} -% } -% \subfloat[Outgassing flux (W/Cu)]{% -% \label{fig: outgassing flux w cu} -% \includegraphics[width=0.5\linewidth]{Figures/Chapter3/monoblocks/interface_condition/w_cu/comparison_fluxes.pdf} -% } \\ -% \subfloat[Solute profiles at steady state (Cu/EUROFER)]{% -% \label{fig: solute profiles cu eurofer} -% \begin{overpic}[width=0.5\linewidth]{Figures/Chapter3/monoblocks/interface_condition/cu_eurofer/solute_profiles_cu_eurofer.pdf} -% \put(35, 55){Cu} -% \put(65, 35){EUROFER} -% \end{overpic} -% } -% \subfloat[Outgassing flux (Cu/EUROFER)]{% -% \label{fig: outgassing flux cu eurofer} -% \includegraphics[width=0.5\linewidth]{Figures/Chapter3/monoblocks/interface_condition/cu_eurofer/comparison_fluxes_cu_eurofer.pdf} -% } -% \caption{Influence of chemical potential conservation} -% \label{fig: influence of mu bi material} -% \end{figure*} - -% In this case, the conservation of chemical potential resulted in higher steady-state concentration gradients (see Figure \ref{fig: solute profiles w cu}) due to the higher solubility of Cu. -% For a given temperature (and therefore given diffusion coefficients), this implied an increase of the outgassing flux (see Figure \ref{fig: outgassing flux w cu}) compared to the case with concentration continuity. - -% \subsection{Cu/EUROFER case} - -% A \SI{4}{mm}-thick slab made of \SI{2}{mm} of Cu (referred as $\Omega_1$) and \SI{2}{mm} of EUROFER (referred as $\Omega_2$) at $T=\SI{600}{K}$ was simulated. -% Since the solubility of EUROFER is lower than that of Cu, the steady-state concentration gradients (see Figure \ref{fig: solute profiles cu eurofer}) were lower compared to the case with concentration continuity. -% The outgassing flux was therefore lower in the case of chemical potential conservation (see Figure \ref{fig: outgassing flux cu eurofer}). - -% \subsection{Identification technique} -% Assuming the diffusion coefficients are known, the solubility coefficients in both materials can be identified by determining an effective diffusion coefficient. - -% The steady-state flux $\varphi_\infty$ can be expressed from Equations \ref{eq:MES c} and \ref{eq: MES c coefficients} as follow: -% \begin{subequations} -% \begin{align} -% \varphi_\infty &= -D_2 \nabla c_2 = -D_1 \nabla c_1 \\ -% &= -D_2 a_2 \frac{c_\mathrm{m}(x=0)}{L} = -D_1 a_1 \frac{c_\mathrm{m}(x=0)}{L}\\ -% &= -a_0 D_\mathrm{eq} \frac{c_\mathrm{m}(x=0)}{L} -% \end{align} -% \label{eq: steady state flux 1} -% \end{subequations} -% where the indexes $1$ and $2$ denote the left and right subdomains respectively and $L$ is the size of the domain in total. - -% If this method allows to measure solubilities, it is however not always convenient considering the time required to reach steady-state. -% One way to overcome this difficulty is to compute an equivalent effective diffusion coefficient noted $D_\mathrm{eff}$. -% $D_\mathrm{eff}$ is computed by assuming an homogeneous material and a linear steady state profile. -% The steady-state flux can therefore be written as: -% \begin{subequations} -% \begin{align} -% \varphi_\infty &= -D_\mathrm{eff} \nabla c \\ -% &= -D_\mathrm{eff} \frac{c_\mathrm{m}(x=L) - c_\mathrm{m}(x=0)}{L} \\ -% \end{align} -% \label{eq: steady state flux 2} -% \end{subequations} - -% By combining Equations \ref{eq: steady state flux 1} and \ref{eq: steady state flux 2}, $D_\mathrm{eff}$ reads: -% \begin{equation} -% D_\mathrm{eff} = \frac{a_0 \; D_\mathrm{eq} \; c_\mathrm{m}(x=0) }{c_\mathrm{m}(x=L) - c_\mathrm{m}(x=0)} -% \end{equation} - -% By fitting measurements of the outgassing flux with either an analytical transient solution or a simulation code (see Figures \ref{fig: outgassing flux w cu} and \ref{fig: outgassing flux cu eurofer}), one can estimate $D_\mathrm{eff}$ and therefore the coefficient $a_0$ which can finally be correlated to material properties (see Equation \ref{eq: MES c coefficients}). - -% However, some discrepancies were found between this method and the actual outgassing curve during the transient phase. -% One way of getting rid of these is to fit the curve with an analytical solution of transient mass transfer in a 1D composite slab with conservation of chemical potential. -% This can be utterly complex and is well beyond the scope of this study. - -% Moreover, surface effects and the presence of traps often complicate the analysis of the experimental data. -% Therefore, a more thorough identification technique would be to use embedded hydrogen transport codes such as FESTIM in a parametric optimisation algorithm as described in previous work \sidecite{delaporte-mathurin_parametric_2021}. -% Such a process could be able to determine materials properties such as diffusion coefficients, solubilities and trap densities. - -\subsection{Methodology} -\subsubsection{Geometry} -The 2D geometry is defined on Figure \ref{fig: monoblock 2d geometry}. - -\begin{figure} - % \subfloat[1D geometry \label{fig: monoblock 1D geometry}]{% - % \begin{overpic}[width=0.5\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/Monoblock 1D.pdf} - % \put(40, 50){\SI{6}{mm}} - % \put(40, 8){W} - % \put(62, 50){\SI{1}{mm}} - % \put(65, 8){Cu} - % \put(72, 50){\SI{1.5}{mm}} - % \put(72, 8){CuCrZr} - % \put(6, 25){\large$\Gamma_\mathrm{top}$} - % \put(85, 25){\large$\Gamma_\mathrm{coolant}$} - % \end{overpic} - % } - \subfloat[2D geometry]{% - \begin{overpic}[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/monoblock_sketch.pdf} - \put(42, 5){\SI{28}{mm}} - \put(97, 50){\SI{28}{mm}} - \put(10, 32){\SI{13.5}{mm}} - \put(42, 62){ \diameter \SI{12}{mm}} - \put(42, 71){ \diameter \SI{15}{mm}} - \put(42, 76){ \diameter \SI{17}{mm}} - \put(20, 80){\large$\Gamma_\mathrm{top}$} - \put(4, 60){\large$\Gamma_\mathrm{lateral}$} - \put(78, 60){\large$\Gamma_\mathrm{lateral}$} - \put(40, 41){\large$\Gamma_\mathrm{coolant}$} - \end{overpic} - } - \caption{2D ITER monoblock geometry showing W armour \cruleme[grey]{0.3cm}{0.3cm}, Cu interlayer \cruleme[orange]{0.3cm}{0.3cm}, CuCrZr alloy cooling pipe \cruleme[yellow]{0.3cm}{0.3cm}}\label{fig: monoblock geometry} - \label{fig: monoblock 2d geometry} - \end{figure} - -\subsubsection{Materials properties} -The materials properties that have been set are detailed in Table \ref{tab:materials properties_1} and their thermal dependency is shown on Figure \ref{fig:properties_1}. -The trap properties in each material are detailed in Table \ref{tab:traps monoblock_1}. -All traps are homogeneously distributed in the materials, except for Trap 2 which is only located in the first micrometre behind the plasma facing surface $\Gamma_\mathrm{top}$ (see Figure \ref{fig: monoblock geometry}) to account for damage creation. - -\begin{table*} - \centering - \begin{tabular}{p{1.7cm} R{3cm} R{3cm} R{1.8cm} R{1cm} R{1.8cm} R{1cm}} - & \multicolumn{2}{c}{Thermal properties} & \multicolumn{4}{c}{Hydrogen transport properties}\\ - \hline - Material & $\rho \cdot C_p \newline(\si{J.K^{-1}.m^{-3}})$ & $\lambda \newline(\si{W.m^{-1}.K^{-1}})$ & $D_0 \newline(\si{m^2.s^{-1}})$ & $E_\mathrm{diff} \newline(\si{eV})$ & $S_0 \newline(\si{m^{-3}.Pa^{-0.5}})$ & $E_\mathrm{S} \newline(\si{eV})$\\ - \hline - \\ - W \cite{frauenfelder_solution_1969}& % - $5.1\times 10^{-6} \cdot T^3 \newline - 8.3\times 10^{-2}\cdot T^2 \newline + 6.0 \times 10^{2}\cdot T \newline +2.4\times 10^6$ &% - $-7.8\times 10^{-9}\cdot T^3 \newline % - +5.0\times 10^{-5}\cdot T^2 \newline% - -1.1\times 10^{-1} \cdot T \newline% - +1.8\times 10^{2}$ &% - $2.4\times 10^{-7}$ & 0.39 &% - $1.87\times 10^{24}$ & 1.04\\ - \\ - Cu \cite{reiter_compilation_1996}&% - $1.7\times 10^{-4}\cdot T^3\newline % - +6.1\times 10^{-2}\cdot T^2\newline % - +4.7\times 10^2\cdot T\newline % - +3.5\times 10^6$ &% - - $-3.9\times 10^{-8}\cdot T^3\newline % - +3.8\times 10^{-5}\cdot T^2\newline % - -7.9\times 10^{-2}\cdot T\newline % - +4.0\times 10^2 $&% - - $6.6\times 10^{-7}$ &% - 0.39&% - $3.14\times 10^{24}$ & 0.57\\ - \\ - CuCrZr \cite{serra_hydrogen_1998}& % - $-1.8\times 10^{-4}\cdot T^3 \newline % - +1.5\times 10^{-1}\cdot T^2\newline % - +6.2\times 10^2\cdot T\newline % - +3.5\times 10^6$ &% - - $5.3\times 10^{-7}\cdot T^3\newline % - -6.5\times 10^{-4}\cdot T^2\newline % - +2.6\times 10^{-1}\cdot T\newline % - +3.1\times 10^2$ & % - - $3.9\times 10^{-7}$ & % - 0.42&% - $4.28\times 10^{23}$ & 0.39\\ - \\ - EUROFER \cite{aiello_hydrogen_2002} & % - - & - & - $1.5\times 10^{-7}$ & % - 0.15 & % - $6.14\times 10^{20}$ & 0.25 - \\ - \\ - \end{tabular} - \caption{Materials properties used in the simulations. Thermal properties are fitted from ANSYS.} - \label{tab:materials properties_1} -\end{table*} - -\begin{figure} - \centering - \begin{subfigure}{\linewidth} - \centering - \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/thermal_prop.pdf} - \caption{Thermal properties} - \end{subfigure} - \begin{subfigure}{\linewidth} - \centering - \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/H_properties.pdf} - \caption{H transport properties} - \end{subfigure} - \caption{Material properties used in the simulations \cite{frauenfelder_solution_1969, reiter_compilation_1996, serra_hydrogen_1998, aiello_hydrogen_2002}} - \label{fig:properties_1} -\end{figure} - -\begin{table*} - \centering - \begin{tabular}{L{1.5cm} L{1.5cm} R{1.6cm} R{1.1cm} R{1.6cm} R{1.1cm} R{2cm}} - & Material & $k_0 (\si{m^3.s^{-1}})$ & $E_k (\si{eV})$ & $p_0 (\si{s^{-1}})$ & $E_p (\si{eV})$ & $n_i (\si{at.fr.})$ \\ - \hline - \\ - Trap 1 & W & $3.8 \times 10^{-17}$ & 0.39 & $8.4 \times 10^{12}$& 1.20 & $5.0 \times 10^{-4}$ \\ - \\ - Trap 2 & W & $3.8 \times 10^{-17}$ & 0.39 & $8.4 \times 10^{12}$& 1.40 & $5.0 \times 10^{-3}$ \\ - \\ - Trap 3 & Cu & $6.0 \times 10^{-17}$ & 0.39 & $8.0 \times 10^{13}$ & 0.50 &$5.0 \times 10^{-5}$\\ - \\ - Trap 4 & CuCrZr & $1.2\times 10^{-16}$ & 0.42 & $8.0 \times 10^{13}$ & 0.50 &$5.0 \times 10^{-5}$\\ - \\ - Trap 5 & CuCrZr & $1.2\times 10^{-16}$ & 0.42 & $8.0 \times 10^{13}$ & 0.83 &$4.0 \times 10^{-2}$\\ - \\ - \end{tabular} - \caption{Traps properties used in the simulations \cite{hodille_macroscopic_2015, dolan_assessment_1994}} - \label{tab:traps monoblock_1} -\end{table*} - - -\subsubsection{Boundary conditions} -The source term $\varphi_\mathrm{imp}$ is equal to \SI{5e23}{m^{-2}.s^{-1}} and its spatial distribution $U(\textbf{x})$ is: - -\begin{equation} - U(\textbf{x}) = \begin{cases} - R_p^{-1},& \text{ if } x < R_p\\ - 0,& \text{ else } - \end{cases} -\end{equation} -where $R_p = \SI{2.5}{nm}$ is the implantation range. -Since the implantation range is very small compared to the monoblock dimensions, this source is equivalent to applying a Dirichlet boundary condition on the exposed surface (see Section \ref{triangle model}). -The value of this boundary condition therefore depends on $\varphi_\mathrm{imp}$, the implantation range $R_p$ and the diffusion coefficient $D$. - -This boundary condition accounts for recombination on the lateral sides of the monoblock. -\begin{subequations} - \begin{align} - T &= \SI{1200}{K}\quad \text { on } \Gamma_\mathrm{top}\\ - c_\mathrm{m} &= \frac{\varphi_\mathrm{imp} \cdot R_p}{D}\quad \text { on } \Gamma_\mathrm{top}\\ - T &= \SI{373}{K}\quad \text { on } \Gamma_\mathrm{coolant}\\ - -D \nabla c_\mathrm{m} \cdot \vec{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad \text { on } \Gamma_\mathrm{coolant} \\ - c_\mathrm{m} &= 0 \quad \text { on } \Gamma_\mathrm{lateral} - \end{align} -\end{subequations} - -with $\varphi_\mathrm{imp} = \SI{5e23}{m^{-2}.s^{-1}}$ the implanted particle flux, $R_p = \SI{1.25}{nm}$ the implantation depth, $\vec{n}$ the normal vector and $K_\mathrm{CuCrZr} = 2.9 \times 10^{-14}\cdot \exp{(-1.92/(k_B\cdot T))}$ the recombination coefficient of the copper alloy (in vacuum) expressed in \si{m^4.s^{-1}} \sidecite{anderl_deuterium_1999}. - - -\subsection{Results} -% TODO : redo this figure with profiles extracted from the 2D field? -% \begin{figure} -% \centering -% \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/comparison_profiles.pdf} -% \caption{Comparison of concentrations profiles at several times} -% \label{fig: concentrations profiles 1D} -% \end{figure} - - -The steady-state temperature field exhibits high temperature gradients between the plasma-facing surface and the cooling surface (see Figure \ref{fig:2D temperature monoblock}). +% The steady-state temperature field exhibits high temperature gradients between the plasma-facing surface and the cooling surface (see Figure \ref{fig:2D temperature monoblock}). \begin{figure} \centering @@ -281,6 +13,8 @@ \subsection{Results} \label{fig:2D temperature monoblock} \end{figure} + +% TODO replace this figure!!! \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/comparison_inventory_2d.pdf} diff --git a/chapters/chapter3/monoblocks/parametric_study.tex b/chapters/chapter3/monoblocks/parametric_study.tex index bfa104f..f813116 100644 --- a/chapters/chapter3/monoblocks/parametric_study.tex +++ b/chapters/chapter3/monoblocks/parametric_study.tex @@ -17,22 +17,6 @@ \subsection{Simulation description} The monoblock model has one trap per material for the sake of simplicity and computational time, but the method could be applied to any set of trapping parameters. -\begin{table*} [ht] - \centering - \begin{tabular}{L{1.5cm} L{1.5cm} R{1.6cm} R{1.1cm} R{1.6cm} R{1.1cm} R{2cm}} - & Material & $k_0 (\si{m^3.s^{-1}})$ & $E_k (\si{eV})$ & $p_0 (\si{s^{-1}})$ & $E_p (\si{eV})$ & $n_i (\si{at.fr.})$ \\ - \hline - \\ - Trap 1 & W & $3.1 \times 10^{-16}$ & 0.20 & $8.4 \times 10^{12}$& 1.00 & $1.1 \times 10^{-3}$ \\ - \\ - Trap 2 & Cu & $6.0 \times 10^{-17}$ & \textcolor{black}{0.39} & $8.0 \times 10^{13}$ & 0.50 &$5.0 \times 10^{-5}$\\ - \\ - Trap 3 & CuCrZr & $1.2 \times 10^{-16}$ & \textcolor{black}{0.42} & $8.0 \times 10^{13}$ & 0.85 &$5.0 \times 10^{-5}$\\ - \\ - \end{tabular} - \caption{Traps properties used in the simulations \cite{hodille_macroscopic_2015, dolan_assessment_1994}} - \label{tab:traps monoblock} -\end{table*} \subsubsection{Boundary conditions} From 9c8da88982ce566c3c71bdce62478dc14e4a3384 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 20:01:07 +0200 Subject: [PATCH 03/22] new script for H transport properties in monoblocks --- .../monoblocks_H_transport_properties.pdf | Bin 0 -> 17959 bytes scripts/plot_properties.py | 68 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zBLd$G9Mix0W%xHf09TE5=EqNbK)?ajaZkP=z+8@L0U+QM^0;*D-;W`gF7|EpoBR2` zU1RV6D*`tEwcG!m|Kyz@0NMZ?lMK+|cZdA%UjPubu>u{(Aw^}N->U)6`Yv9Jpf$r0f@rG#U10~Xbtj(i6BHELZFKnjEDDGQBl`_ABnhoIRK3SWM}JR z1N`lPA6t3Y+JmgEY@C64`ql&g4?6Srva=__?r|i5llk@!@F57mJncdM(y(9=`w!&y zjRrv?u}kO|8g|?KjfS=VU+Q7^vfpUHzWy5x18r mcX#aeckB!F90P$jx^KtJR$iFn?F51pgP}>dxfQe&N&XMCemiCW literal 0 HcmV?d00001 diff --git a/scripts/plot_properties.py b/scripts/plot_properties.py new file mode 100644 index 0000000..e39417b --- /dev/null +++ b/scripts/plot_properties.py @@ -0,0 +1,68 @@ +import h_transport_materials as htm +import matplotlib.pyplot as plt + +diffusivity_w = htm.diffusivities.filter( + material="tungsten", author="fernandez", isotope="h" +)[0] +diffusivity_cu = htm.diffusivities.filter(material="copper", author="reiter")[0] +diffusivity_cucrzr = htm.diffusivities.filter(material="cucrzr", author="serra")[5] + +solubility_w = htm.solubilities.filter(material="tungsten", author="frauenfelder")[0] +solubility_cu = htm.solubilities.filter(material="copper", author="reiter")[0] +solubility_cucrzr = htm.solubilities.filter(material="cucrzr", author="serra")[1] + + +def thermal_cond_W(T): + return -7.84154e-9 * T**3 + 5.03006e-5 * T**2 - 1.07335e-1 * T + 1.75214e2 + + +def thermal_cond_Cu(T): + return -3.93153e-08 * T**3 + 3.76147e-05 * T**2 - 7.88669e-02 * T + 4.02301e02 + + +def thermal_cond_CuCrZr(T): + return 5.25780e-7 * T**3 - 6.45110e-4 * T**2 + 2.57678e-01 * T + 3.12969e2 + + +def rho_cp_W(T): + return 5.15356e-6 * T**3 - 8.30703e-2 * T**2 + 5.98312e2 * T + 2.48160e6 + + +def rho_cp_Cu(T): + return 1.68402e-4 * T**3 - 6.14079e-2 * T**2 + 4.67353e2 * T + 3.45899e6 + + +def rho_cp_CuCrZr(T): + return -1.79134e-4 * T**3 - 1.51383e-1 * T**2 + 6.22091e2 * T + 3.46007e6 + + +grey_W = "tab:grey" +orange_Cu = (228 / 255, 146 / 255, 64 / 255) +yellow_CuCrZr = (180 / 255, 95 / 255, 6 / 255) + +fig, axs = plt.subplots(2, 1, sharex=True) + +plt.sca(axs[0]) +htm.plotting.plot(diffusivity_w, label="W", color=grey_W) +htm.plotting.plot(diffusivity_cu, label="Cu", color=orange_Cu) +htm.plotting.plot(diffusivity_cucrzr, label="CuCrZr", color=yellow_CuCrZr) +plt.xlabel("") +plt.yscale("log") +plt.ylabel("Diffusivity (m$^2$ s$^{-1}$)") +htm.plotting.line_labels() + +plt.sca(axs[1]) +htm.plotting.plot(solubility_w, label="W", color=grey_W) +htm.plotting.plot(solubility_cu, label="Cu", color=orange_Cu) +htm.plotting.plot(solubility_cucrzr, label="CuCrZr", color=yellow_CuCrZr) +plt.yscale("log") +plt.ylabel("Solubility (m$^{-3}$ Pa$^{-1/2}$)") +htm.plotting.line_labels() + +for ax in axs: + ax.spines.right.set_visible(False) + ax.spines.top.set_visible(False) +plt.tight_layout() +plt.show() + +fig, axs = plt.subplots(2, 1, sharex=True) From a2ddcf7b678961b8650b2a17d2e9ba53d55b17aa Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 20:01:14 +0200 Subject: [PATCH 04/22] updated figure --- chapters/chapter3/monoblocks.tex | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index df097fb..e5ec482 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -110,7 +110,7 @@ \section{Model description} \end{subfigure} \begin{subfigure}{\linewidth} \centering - \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/H_properties.pdf} + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/monoblock_H_transport_properties.pdf} \caption{H transport properties} \end{subfigure} \caption{Material properties used in the simulations \cite{frauenfelder_solution_1969, reiter_compilation_1996, serra_hydrogen_1998, aiello_hydrogen_2002}} From dd0643582f0f1c7f76c434bcdee4783d335f84fd Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 20:02:51 +0200 Subject: [PATCH 05/22] renamed figure --- ...ies.pdf => monoblock_H_transport_properties.pdf} | Bin 1 file changed, 0 insertions(+), 0 deletions(-) rename Figures/Chapter3/monoblocks/{monoblocks_H_transport_properties.pdf => monoblock_H_transport_properties.pdf} (100%) diff --git a/Figures/Chapter3/monoblocks/monoblocks_H_transport_properties.pdf b/Figures/Chapter3/monoblocks/monoblock_H_transport_properties.pdf similarity index 100% rename from Figures/Chapter3/monoblocks/monoblocks_H_transport_properties.pdf rename to Figures/Chapter3/monoblocks/monoblock_H_transport_properties.pdf From de72179af45822a65e27cf1584fdc2706f44ef33 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 21:27:21 +0200 Subject: [PATCH 06/22] fixed appendix --- chapters/demo_monoblock.tex | 3 +++ 1 file changed, 3 insertions(+) diff --git a/chapters/demo_monoblock.tex b/chapters/demo_monoblock.tex index e47d2c3..36c1f3f 100644 --- a/chapters/demo_monoblock.tex +++ b/chapters/demo_monoblock.tex @@ -1,3 +1,6 @@ +\setchapterstyle{lines} +\labpage{DEMO monoblocks} +\chapter{DEMO monoblocks} So far, only 2D monoblocks simulations were run, assuming an infinite thickness (or assuming no desorption from the poloidal gaps). The goal of this section is to assess the influence of 3D edge effects on the monoblocks simulation results. It will be shown that the error induced by 2D assumption decreases for thick monoblocks. From ea1e8696522290f2a560c97efc0f6022f306ef7d Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 21:39:14 +0200 Subject: [PATCH 07/22] added label --- chapters/demo_monoblock.tex | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/chapters/demo_monoblock.tex b/chapters/demo_monoblock.tex index 36c1f3f..f75e76e 100644 --- a/chapters/demo_monoblock.tex +++ b/chapters/demo_monoblock.tex @@ -1,6 +1,6 @@ \setchapterstyle{lines} \labpage{DEMO monoblocks} -\chapter{DEMO monoblocks} +\chapter{DEMO monoblocks}\labch{DEMO monoblocks} So far, only 2D monoblocks simulations were run, assuming an infinite thickness (or assuming no desorption from the poloidal gaps). The goal of this section is to assess the influence of 3D edge effects on the monoblocks simulation results. It will be shown that the error induced by 2D assumption decreases for thick monoblocks. From e8cb1e5ac0c422da3e8731cadf573b9bd860b5f9 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 21:39:29 +0200 Subject: [PATCH 08/22] text in model description + dimensionality --- chapters/chapter3/monoblocks.tex | 65 +++++++++++++++++++++++++------- 1 file changed, 51 insertions(+), 14 deletions(-) diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index e5ec482..ed2e6b5 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -14,6 +14,14 @@ \section{Introduction} \section{Model description} +The monoblock geometry is described on reffig{monoblock geometry}. +The boundary conditions for the heat transfer problem are described in \refeq{bc thermal monoblock} and those for the hydrogen transport problem are described in \refeq{bc H transport monoblock}. +An instantaneous recombination is assumed on the poloidal and toroidal gaps and at the plasma facing surface. +This assumption is consistant with the high recombination coefficient measured by Ogorodnikova \sidecite{ogorodnikova_recombination_2019} compared to Anderl's coefficient \sidecite{anderl_deuterium_1992}. + +The materials properties (diffusivity, solubility, and thermal conductivity, density and heat capacity) are described in \labtab{materials properties monoblock} and plotted on \reffig{properties monoblock}. +Finally, the traps properties are described in \reftab{traps monoblock}. + \begin{figure} \begin{overpic}[width=\linewidth]{Figures/Chapter3/monoblocks/interface_condition/iter case/monoblock_sketch.pdf} \put(42, 5){\SI{28}{mm}} @@ -27,25 +35,25 @@ \section{Model description} \put(78, 60){\large$\Gamma_\mathrm{toroidal}$} \put(40, 41){\large$\Gamma_\mathrm{coolant}$} \end{overpic} - \caption{ITER monoblock geometry showing W armour \cruleme[grey]{0.3cm}{0.3cm}, Cu interlayer \cruleme[orange]{0.3cm}{0.3cm}, CuCrZr alloy cooling pipe \cruleme[yellow]{0.3cm}{0.3cm}. The monoblock thickness is \SI{12}{mm}.}\label{fig: monoblock geometry} - \label{fig: monoblock 2d geometry} + \caption{ITER monoblock geometry showing W armour \cruleme[grey]{0.3cm}{0.3cm}, Cu interlayer \cruleme[orange]{0.3cm}{0.3cm}, CuCrZr alloy cooling pipe \cruleme[yellow]{0.3cm}{0.3cm}. The monoblock thickness is \SI{12}{mm}.} + \labfig{monoblock geometry} \end{figure} \begin{subequations} \begin{align} - -\lambda \vec{\nabla} T \cdot \vec{n} &=\varphi_\mathrm{heat} \quad &\text { on } \Gamma_\mathrm{top}\\ - -\lambda \vec{\nabla} T\cdot \vec{n} &= -h \cdot \left(T_\mathrm{coolant} - T\right)\quad &\text { on } \Gamma_\mathrm{coolant} + -\lambda \nabla T \cdot \mathbf{n} &=\varphi_\mathrm{heat} \quad &\text { on } \Gamma_\mathrm{top}\\ + -\lambda \nabla T\cdot \mathbf{n} &= -h \cdot \left(T_\mathrm{coolant} - T\right)\quad &\text { on } \Gamma_\mathrm{coolant} \end{align} - \label{eq: bc thermal monoblock} + \labeq{bc thermal monoblock} \end{subequations} \begin{subequations} \begin{align} c_\mathrm{m} &= \frac{\varphi_\mathrm{imp} R_p}{D} \quad &\text { on } \Gamma_\mathrm{top}\\ - -D \vec{\nabla} c_\mathrm{m} \cdot \vec{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ + -D \nabla c_\mathrm{m} \cdot \mathbf{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ c_\mathrm{m} &= 0 \quad &\text { on } \Gamma_\mathrm{toroidal} \text{ and } \Gamma_\mathrm{poloidal} \\ \end{align} - \label{eq: bc H transport monoblock} + \labeq{bc H transport monoblock} \end{subequations} \begin{table*} @@ -97,8 +105,8 @@ \section{Model description} \\ \\ \end{tabular} - \caption{Materials properties used in the simulations. Thermal properties are fitted from ANSYS.} - \label{tab:materials properties monoblock} + \caption{Materials properties used in the simulations. Thermal properties are fitted from ANSYS. $T$ is the temperature in \si{K}.} + \labtab{materials properties monoblock} \end{table*} \begin{figure} @@ -114,7 +122,7 @@ \section{Model description} \caption{H transport properties} \end{subfigure} \caption{Material properties used in the simulations \cite{frauenfelder_solution_1969, reiter_compilation_1996, serra_hydrogen_1998, aiello_hydrogen_2002}} - \label{fig:properties monoblock} + \labfig{properties monoblock} \end{figure} \begin{table*} @@ -133,21 +141,50 @@ \section{Model description} \\ \end{tabular} \caption{Traps properties used in the simulations \cite{hodille_macroscopic_2015, dolan_assessment_1994}} - \label{tab:traps monoblock} + \labtab{traps monoblock} \end{table*} \section{Simulation simplifications} -\subsection{Influence of dimension} +\subsection{Influence of dimensionality} + +The first simplification that can be done is the dimensionality. +A full 3D simulation would be the most accurate, but also the most expensive in terms of computaion time. +Conversely, 1D simulations are faster to run, but are less accurate. +This is sometimes refered as the \textit{curse of dimensionality}. +A 2D approximation assumes the solution is independent of the poloidal direction. +The hydrogen inventory is obtained by: + +\begin{equation} + \mathrm{inv} = e \int_\Omega (c_\mathrm{m} + \sum c_\mathrm{t,\, i}) \, dS +\end{equation} +where $e$ is the monoblock thickness. + +Similarily, the 1D approximation assumes the solution is independent of both the poloidal and the toroidal direction (see \reffig{dimension approximations monoblock}). +It also cannot capture the full geometry of the monoblock as it would assume Cu and CuCrZr slabs instead of hollow cylinders. +The hydrogen inventory is obtained by: + +\begin{equation} + \mathrm{inv} = e \, L \int_\Omega (c_\mathrm{m} + \sum c_\mathrm{t,\, i}) \, dl +\end{equation} +where $L$ is the monoblock width. + \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/dimension_approximation.png} - \caption{} + \caption{Representation of the 2D and 1D approximations on a monoblock geometry. The arrows represent geometry independencies.} + \labfig{dimension approximations monoblock} \end{figure} +Monoblocks simulations were run in 1D, 2D, and 3D and the inventory was computed for each case (see \reffig{monoblock inventories 1d 2d 3d}). +Both the 1D and 2D approximations overestimate the inventory compared to the 3D reference, these approximations are therfore conservative. +It should however be noticed that, when neglecting the recombination on the poloidal gap (\textit{ie} assuming hydrogen cannot desorb from this surface), the 2D approximation is strictly equivalent to the 3D reference (see \refch{DEMO monoblocks}). +For these reasons, the 2D approximation will be employed in the following sections as it is the best compromise between accuracy and computational time. + \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/3D_monoblocks/comparison_inventory_1d_2d_3d.pdf} - \caption{} + \caption{Comparison of monoblock inventories for the 1D, 2D approximations and the 3D case.} + \labfig{monoblock inventories 1d 2d 3d} \end{figure} \subsection{Influence of interface condition} From f809a6f61c1c90068aab8714c91ef5a52d3493ac Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Tue, 14 Jun 2022 21:47:05 +0200 Subject: [PATCH 09/22] added values for boundary conditions --- chapters/chapter3/monoblocks.tex | 4 +++- 1 file changed, 3 insertions(+), 1 deletion(-) diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index ed2e6b5..3f7e79b 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -46,15 +46,17 @@ \section{Model description} \end{align} \labeq{bc thermal monoblock} \end{subequations} +where $\varphi_\mathrm{heat} = \SI{10}{MW.m^{-2}}$, $T_\mathrm{coolant} = \SI{323}{K}$ and $h = \SI{70000}{W.m^{-2}.K^{-1}}$. \begin{subequations} \begin{align} c_\mathrm{m} &= \frac{\varphi_\mathrm{imp} R_p}{D} \quad &\text { on } \Gamma_\mathrm{top}\\ - -D \nabla c_\mathrm{m} \cdot \mathbf{n} &= K_\mathrm{CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ + -D \nabla c_\mathrm{m} \cdot \mathbf{n} &= K_\mathrm{r, \, CuCrZr} \cdot c_\mathrm{m}^{2} \quad &\text { on } \Gamma_\mathrm{coolant} \\ c_\mathrm{m} &= 0 \quad &\text { on } \Gamma_\mathrm{toroidal} \text{ and } \Gamma_\mathrm{poloidal} \\ \end{align} \labeq{bc H transport monoblock} \end{subequations} +where $\varphi_\mathrm{imp} = \SI{1.6e22}{m^{-2}.s^{-1}}$, $R_p = \SI{1}{nm}$, and $K_\mathrm{r, \, CuCrZr} = 2.9 \times 10^{-14}\cdot \exp{(-1.92/(k_B\cdot T))}$ the recombination coefficient of the copper alloy (in vacuum) expressed in \si{m^4.s^{-1}} \sidecite{anderl_deuterium_1999}. \begin{table*} \centering From f1873ca3944ae73839cdf1c6e7bb367f636d6c83 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Wed, 15 Jun 2022 10:38:11 +0200 Subject: [PATCH 10/22] added a section on cycling --- .../comparison_inventory_cycling.pdf | Bin 17267 -> 18262 bytes 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Oz!MR&vIdrhi2nt1ZRyGY literal 0 HcmV?d00001 diff --git a/bibfile.bib b/bibfile.bib index f4558f1..ad75764 100644 --- a/bibfile.bib +++ b/bibfile.bib @@ -1,5219 +1,5176 @@ -@article{sun_critical_2014, - title = {Critical concentration for hydrogen bubble formation in metals}, - volume = {26}, - issn = {0953-8984}, - doi = {10.1088/0953-8984/26/39/395402}, - abstract = {Employing a thermodynamic model with previously calculated first-principle energetics as inputs, we determined the hydrogen (H) concentration at the interstitial and monovacancy as well as its dependence on temperature and pressure in tungsten and molybdenum. Based on this, we predicted the critical H concentration for H bubble formation at different temperatures. The critical concentration, defined as the value when the concentration of H at a certain mH-vacancy complex first became equal to that of H at the interstitial, was 24 ppm/7.3 GPa and 410 ppm/4.7 GPa at 600 K in tungsten and molybdenum in the case of a monovacancy. Beyond the critical H concentration, numerous H atoms accumulated in the monovacancy, leading to the formation and rapid growth of H-vacancy complexes, which was considered the preliminary stage of H bubble formation. We expect that the proposed approach will be generally used to determine the critical H concentration for H bubble formation in metals.}, +@article{holzner_solute_2020, + title = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment}, + volume = {T171}, + issn = {1402-4896}, + url = {https://doi.org/10.1088/1402-4896/ab4b42}, + doi = {10.1088/1402-4896/ab4b42}, + abstract = {The diffusion of protium and deuterium in tungsten is measured in gas loading experiments as a function of temperature for a hydrogen isotope loading pressure of 500 mbar and temperatures between 1600 K and 2600 K. The diffusion parameters are measured from the degassing rates of both a single-crystalline and a polycrystalline tungsten cylinder by mass spectrometry. The data are analysed assuming an Arrhenius-like temperature dependence of the diffusivity and following the classical analysis approach of Frauenfelder (1969 J. Vac Sci. Technol. 6, 388). For deuterium in tungsten an activation energy of 0.06 eV is obtained. For protium the activation energy is identical within the uncertainty limits.}, language = {en}, - number = {39}, - journal = {Journal of Physics: Condensed Matter}, - author = {Sun, Lu and Jin, Shuo and Zhou, Hong-Bo and Zhang, Ying and Zhang, Wenqing and Ueda, Y. and Lee, H. T. and Lu, Guang-Hong}, - month = sep, - year = {2014}, - keywords = {Bubble, Density Functional Theory}, - pages = {395402}, - file = {Sun et al. - 2014 - Critical concentration for hydrogen bubble formati.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MLA7WRM3\\Sun et al. - 2014 - Critical concentration for hydrogen bubble formati.pdf:application/pdf}, + urldate = {2022-03-15}, + journal = {Physica Scripta}, + author = {Holzner, G. and Schwarz-Selinger, T. and Dürbeck, T. and Toussaint, U. von}, + month = jan, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {014034}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\Q8RAWZVY\\Holzner et al. - 2020 - Solute diffusion of hydrogen isotopes in tungsten—.pdf:application/pdf}, } -@article{schmid_comparison_2012, - title = {Comparison of hydrogen retention in {W} and {W}/{Ta} alloys}, - volume = {426}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311512001730}, - doi = {10.1016/j.jnucmat.2012.04.003}, - abstract = {The extreme brittleness of tungsten (W) is one of the challenges of using W as first wall material. One attempt to alleviate this problem is to use W alloys with better mechanical properties. However these alloying elements must not degrade the favorable properties of W with respect to its application at the first wall of fusion devices: low sputter yield and hydrogen inventory. In this work we investigate the hydrogen retention in the recently proposed W/Ta alloys under deuterium ion bombardment. By directly comparing pure W and W/Ta alloys with 1\% and 5\% Ta content we found that the W/Ta alloys retain significantly more hydrogen than pure W under identical implantation conditions. Our finding of increased hydrogen retention together with the fact that the Ta alloying did not improve the brittleness makes W/Ta alloys an unacceptable choice for the first wall of fusion devices.}, +@article{zhou_molecular_2016, + title = {Molecular {Dynamics} {Simulations} of {Hydrogen} {Diffusion} in {Aluminum}}, + volume = {120}, + issn = {1932-7447, 1932-7455}, + url = {https://pubs.acs.org/doi/10.1021/acs.jpcc.6b01802}, + doi = {10.1021/acs.jpcc.6b01802}, language = {en}, - number = {1}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Schmid, K. and Rieger, V. and Manhard, A.}, - month = jul, - year = {2012}, - keywords = {Experiment}, - pages = {247--253}, - file = {Schmid et al. - 2012 - Comparison of hydrogen retention in W and WTa all.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5M529LGL\\Schmid et al. - 2012 - Comparison of hydrogen retention in W and WTa all.pdf:application/pdf}, + number = {14}, + urldate = {2022-03-15}, + journal = {The Journal of Physical Chemistry C}, + author = {Zhou, X. W. and El Gabaly, F. and Stavila, V. and Allendorf, M. D.}, + month = apr, + year = {2016}, + pages = {7500--7509}, + file = {Zhou et al. - 2016 - Molecular Dynamics Simulations of Hydrogen Diffusi.pdf:D\:\\Logiciels\\data_zotero\\storage\\5XV8FV8H\\Zhou et al. - 2016 - Molecular Dynamics Simulations of Hydrogen Diffusi.pdf:application/pdf}, } -@article{quiros_blister_2017, - series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, - title = {Blister formation and hydrogen retention in aluminium and beryllium: {A} modeling and experimental approach}, - volume = {12}, - issn = {2352-1791}, - shorttitle = {Blister formation and hydrogen retention in aluminium and beryllium}, - doi = {10.1016/j.nme.2016.12.036}, - abstract = {Experiments were performed in a low pressure-high density plasma reactor in order to study the impact of hydrogen retention in aluminium under plasma conditions. Microscopy scans of the surface were performed before and after 1h plasma exposure (fluence 6.1 ×1023ions/m2) where it is seen that blisters start to nucleate at the grain boundaries. Investigation on blister growth kinetics was performed for fluences ranging between 6 ×1023 and 3.7 ×1024ions/m2. The evolution of the characteristic size of the projected area was also analyzed. Finally, a macroscopic rate equations (MRE) code was used to simulate hydrogen retention and diffusion in Al and bubble growth in the bulk was simulated using experimental results. This model was also used to simulate these phenomena in Be and compare its behavior with respect to Al.}, +@article{fu_trapping_2019, + title = {Trapping and detrapping process of hydrogen in tungsten divacancy: {A} molecular dynamics study}, + volume = {452}, + issn = {0168-583X}, + shorttitle = {Trapping and detrapping process of hydrogen in tungsten divacancy}, + url = {https://www.sciencedirect.com/science/article/pii/S0168583X19303714}, + doi = {10.1016/j.nimb.2019.05.050}, + abstract = {In future fusion devices, tungsten (W) and W-based alloys are the primary candidates for plasma facing materials, which experience high-energy neutron and high-flux hydrogen (H) isotopes and helium. Since mono-vacancy and di-vacancy are considered respectively as the common point defect and cluster under irradiation, the interaction between H and vacancies is concerned. In this work, the models to abstract the dynamical parameters, including the effective capture radii (ECRs) and dissociation coefficients, for various trapping and dissociation processes (VnHx + H ⇌ VnHx+1), were firstly extended based on molecular dynamics (MD) simulations. It was found that the ECRs and dissociation coefficients are dependent not only on the reaction types but also on the temperatures. As the increase of the trapped H atoms in the mono-/di-vacancy, the ECRs decrease gradually and the dissociation energies of H decrease gradually. It is not always valid that ECR is commonly assumed as one lattice constant or pre-exponential factor is commonly assumed as 10 ps−1. The number of trapped H in the vacancies should be related to the dwell time, and is also related to the temperature. These results should be potentially applicable for the long-term simulation methods such as kinetic Monte Carlo (KMC) and rate theory (RT) models.}, language = {en}, - journal = {Nuclear Materials and Energy}, - author = {Quirós, C. and Mougenot, J. and Lombardi, G. and Redolfi, M. and Brinza, O. and Charles, Y. and Michau, A. and Hassouni, K.}, + urldate = {2022-03-15}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Fu, Baoqin and Qiu, Mingjie and Cui, Jiechao and Li, Min and Wang, Jun and Hou, Qing}, month = aug, - year = {2017}, - keywords = {Experiment, Macroscopic rate equations}, - pages = {1178--1183}, - file = {Quirós et al. - 2017 - Blister formation and hydrogen retention in alumin.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2FEKSEVD\\Quirós et al. - 2017 - Blister formation and hydrogen retention in alumin.pdf:application/pdf}, + year = {2019}, + keywords = {Detrapping, Hydrogen, Molecular dynamics, Tungsten, Vacancy}, + pages = {21--25}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4WEL5JCK\\S0168583X19303714.html:text/html}, } -@article{lu_review_2014, - title = {A review of modelling and simulation of hydrogen behaviour in tungsten at different scales}, - volume = {54}, - issn = {0029-5515}, - doi = {10.1088/0029-5515/54/8/086001}, - abstract = {Tungsten (W) is considered to be one of the most promising plasma-facing materials (PFMs) for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely high fluxes of low-energy hydrogen (H) isotopes, leading to retention of H isotopes and blistering in W, which will degrade the thermal and mechanical properties of W. Modelling and simulation are indispensable to understand the behaviour of H isotopes including dissolution, diffusion, accumulation and bubble formation, which can contribute directly to the design, preparation and application of W as a PFM under a fusion environment. This paper reviews the recent findings regarding the behaviour of H in W obtained via modelling and simulation at different scales.}, +@article{einstein_uber_1905, + title = {Über die von der molekularkinetischen {Theorie} der {Wärme} geforderte {Bewegung} von in ruhenden {Flüssigkeiten} suspendierten {Teilchen}}, + volume = {322}, + issn = {1521-3889}, + url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/andp.19053220806}, + doi = {10.1002/andp.19053220806}, language = {en}, number = {8}, - journal = {Nuclear Fusion}, - author = {Lu, Guang-Hong and Zhou, Hong-Bo and Becquart, Charlotte S.}, - month = jul, - year = {2014}, - keywords = {Density Functional Theory}, - pages = {086001}, - file = {Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3ANYZCGN\\Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:application/pdf;IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z7Y5TL4T\\Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:application/pdf}, -} - -@article{zhang_hydrogen_2018, - series = {Special {Section} on "18th {International} {Conference} on {Fusion} {Reactor} {Materials}"}, - title = {Hydrogen diffusion behavior in tungsten under anisotropic strain}, - volume = {511}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311517317889}, - doi = {10.1016/j.jnucmat.2018.05.061}, - abstract = {In future fusion devices, the incident hydrogen plasma with high mobility can diffuse deep into tungsten bulk, which is directly relevant with hydrogen isotopes permeation and retention in tungsten. In this work, density functional theory (DFT) and object kinetic Monte Carlo (OKMC) simulations are adopted to investigate the hydrogen diffusion behavior in tungsten under anisotropic uniaxial strain from −2.5\% to 2.5\%. As presented by our DFT calculations, there are two types of hydrogen diffusion paths when applying strain, including one path perpendicular to the strain direction and another path largely along the strain direction. The migration energy barriers of these two paths have opposite variation tendencies in tensile or compressive condition. Our OKMC calculations based on DFT input show that, in tensile condition, the hydrogen diffusion is restrained despite the lower energy barrier of the corresponding diffusion path. In compressive condition, the hydrogen diffusion along the strain direction is enhanced, while that perpendicular to the strain direction is suppressed. The hydrogen diffusivity under anisotropic strain at the temperature range from 400 K to 1800 K is determined. It is demonstrated that tensile strain can suppress the diffusivity, while compressive strain can either suppress or facilitate the diffusivity depending on the temperature and the strain value. The anisotropic strain exhibits distinct effect on hydrogen diffusivity at lower temperature but its effect is minimal as the temperature increases.}, - language = {en}, - urldate = {2019-11-07}, - journal = {Journal of Nuclear Materials}, - author = {Zhang, Xuesong and Xu, Ke and Niu, Liang-Liang and Zhang, Ying and Lu, Guang-Hong}, - month = dec, - year = {2018}, - keywords = {Density Functional Theory, Monte Carlo}, - pages = {574--581}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QS9LLHXK\\Zhang et al. - 2018 - Hydrogen diffusion behavior in tungsten under anis.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CGF9WRII\\S0022311517317889.html:text/html}, + urldate = {2022-03-15}, + journal = {Annalen der Physik}, + author = {Einstein, A.}, + year = {1905}, + note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1002/andp.19053220806}, + pages = {549--560}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\I5VFVCTF\\Einstein - 1905 - Über die von der molekularkinetischen Theorie der .pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZNHJEGNF\\andp.html:text/html}, } -@article{blondel_xolotl:_nodate, - title = {Xolotl: a cluster dynamics code to predict gas bubble evolution in solids}, +@article{wang_molecular_2020, + title = {Molecular dynamics studies of hydrogen diffusion in tungsten at elevated temperature: {Concentration} dependence and defect effects}, + volume = {45}, + issn = {0360-3199}, + shorttitle = {Molecular dynamics studies of hydrogen diffusion in tungsten at elevated temperature}, + url = {https://www.sciencedirect.com/science/article/pii/S0360319919339989}, + doi = {10.1016/j.ijhydene.2019.10.151}, + abstract = {Influence of hydrogen concentration and defects introduced by neutron irradiation on hydrogen diffusion in tungsten has been investigated by molecular dynamics simulation at elevated temperatures. Hydrogen diffusion is shown to be significantly restrained at high concentrations due to spontaneous formation of platelet-like hydrogen clusters. For neutron irradiation defects, self-interstitials, mono-vacancies and vacancy clusters are considered. By clustering and acting as dislocation loops, self-interstitials show considerable trapping effects on hydrogen, leading to the suppression of hydrogen effective diffusion and the change of diffusion model in which hydrogen mainly diffuses along dislocation lines instead of hopping between tetrahedral interstitial sites. Moreover, an equation connecting hydrogen diffusion parameters and the total length of dislocation loops is empirically established. Different influences of mono-vacancies and vacancy clusters on hydrogen diffusion have been carefully identified. With the same vacancy concentration, hydrogen diffusivity is lower with mono-vacancies than that with vacancy clusters because more isolated trapping sites are provided by mono-vacancies. This work is not only helpful for understanding the synergistic effects of neutron irradiation and plasma interaction, but also potentially applicable for larger scale simulations as input data.}, language = {en}, - author = {Blondel, Sophie and Lasa, Ane and Maroudas, Dimitrios and Roth, Philip C}, - keywords = {Bubble, Cluster dynamics}, - pages = {32}, - file = {Blondel et al. - Xolotl a cluster dynamics code to predict gas bub.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CXKFSHD7\\Blondel et al. - Xolotl a cluster dynamics code to predict gas bub.pdf:application/pdf}, + number = {1}, + urldate = {2022-03-15}, + journal = {International Journal of Hydrogen Energy}, + author = {Wang, Li-Fang and Shu, Xiaolin and Lin, De-Ye and Lu, Guang-Hong and Song, Hai-Feng}, + month = jan, + year = {2020}, + keywords = {Molecular dynamics, Tungsten, Hydrogen diffusion, Irradiation defect}, + pages = {822--834}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GDC7BPBN\\S0360319919339989.html:text/html}, } -@article{faney_spatially_2014, - title = {Spatially dependent cluster dynamics modeling of microstructure evolution in low energy helium irradiated tungsten}, - volume = {22}, - issn = {0965-0393}, - url = {https://iopscience.iop.org/article/10.1088/0965-0393/22/6/065010}, - doi = {10.1088/0965-0393/22/6/065010}, - abstract = {In fusion reactors, plasma facing components (PFC) and in particular the divertor will be irradiated with high fluxes of low energy (∼100 eV) helium and hydrogen ions. Tungsten is one of the leading candidate divertor materials for ITER and DEMO fusion reactors. However, the behavior of tungsten under high dose, coupled helium/hydrogen exposure remains to be fully understood. The PFC response and performance changes are intimately related to microstructural changes, such as the formation of point defect clusters, helium and hydrogen bubbles or dislocation loops. Computational materials modeling has been used to investigate the mechanisms controlling microstructural evolution in tungsten following high dose, high temperature helium exposure. The aim of this study is to understand and predict helium implantation, primary defect production and defect diffusion, helium-defect clustering and interactions below a tungsten surface exposed to low energy helium irradiation. The important defects include interstitial clusters, vacancy clusters, helium interstitials and helium-vacancy clusters. We report results from a one-dimensional, spatially dependent cluster dynamics model based on the continuum reaction–diffusion rate theory to describe the evolution in space and time of all these defects. The key parameter inputs to the model (diffusion coefficients, migration and binding energies, initial defect production) are determined from a combination of atomistic materials modeling and available experimental data.}, +@article{liu_hydrogen_2014, + series = {Proceedings of the 16th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-16)}, + title = {Hydrogen diffusion in tungsten: {A} molecular dynamics study}, + volume = {455}, + issn = {0022-3115}, + shorttitle = {Hydrogen diffusion in tungsten}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311514005911}, + doi = {10.1016/j.jnucmat.2014.09.003}, + abstract = {The diffusion behavior of hydrogen (H) in tungsten (W) has been studied by molecular dynamics simulations. The diffusivities from 200K to 3000K are calculated and the diffusion equation is fitted to D=5.13×10−8exp(−0.21eV/kT)m2/s. The diffusion equations in different temperature ranges of 200–500K, 500–2400K and 2400–3000K are also given separately and the results imply different H diffusion modes in different temperature ranges, which is proved by analyzing equilibrium H positions at low and high temperatures. The H atom jumps between different tetrahedral interstitial sites (TISs) at lower temperatures, but the transition to octahedral interstitial sites (OISs) is also observed at high temperatures. Moreover, with a vacancy present in the W system, vacancy trapping of H is observed, and it is shown that the vacancy trapping reduces with the increasing temperature. The H binding energy to monovacancy is obtained using three different methods including NEB and fitting both H diffusivity and time for H to detrap from the vacancy, which provides more information of the H behaviors with the existence of defects.}, language = {en}, - number = {6}, - urldate = {2019-10-28}, - journal = {Modelling and Simulation in Materials Science and Engineering}, - author = {Faney, T. and Wirth, B. D.}, - month = aug, + number = {1}, + urldate = {2022-03-15}, + journal = {Journal of Nuclear Materials}, + author = {Liu, Yi-Nan and Wu, Tiefeng and Yu, Yi and Li, Xiao-Chun and Shu, Xiaolin and Lu, Guang-Hong}, + month = dec, year = {2014}, - keywords = {Bubble, Cluster dynamics}, - pages = {065010}, - file = {Faney et Wirth - 2014 - Spatially dependent cluster dynamics modeling of m.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PTWUZR2T\\Faney et Wirth - 2014 - Spatially dependent cluster dynamics modeling of m.pdf:application/pdf}, + keywords = {molecular dynamics}, + pages = {676--680}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XAHNCMLY\\S0022311514005911.html:text/html}, } -@article{zhang_simulation_2019, - title = {Simulation of migration and coalescence of helium bubbles in nickel}, - volume = {518}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S002231151831434X}, - doi = {10.1016/j.jnucmat.2019.02.023}, - abstract = {The mechanism of migration and coalescence of nanoscale helium bubbles was studied using molecular dynamics. Small helium bubbles in nickel were observed to migrate in a random-walk style at temperatures higher than 0.7 Tm (melting point). Coalescence occurred when two helium bubbles approached each other, leading to the formation of a large bubble. The motion of the helium bubbles in nickel proceeds by displacement of nickel atoms on the surface, which causes the rearrangement of other nickel atoms, resulting surface diffusion. These findings indicate that migration and coalescence may be the possible growth mechanism for small helium bubbles in nickel at high temperature.}, +@article{kembleton_eu-demo_2022, + title = {{EU}-{DEMO} design space exploration and design drivers}, + volume = {178}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379622000801}, + doi = {10.1016/j.fusengdes.2022.113080}, + abstract = {Once the high-level requirements for a fusion power plant are set, the expected performance of plant systems, including the plasma, must be defined and then the available design space for the plant can be explored in order to converge on a final overall plant operating point, setting the major plant parameters such as number of toroidal field (TF) coils, tokamak major radius, plant power flows etc. Such design space explorations are conducted using systems codes which contain simplified models for plant systems, and attempt to capture the interactions between them in order to balance performance trade-offs and enforce overall consistency. This paper summarizes the work carried out to identify the EU-DEMO baseline operating point and the underpinning assumptions about technology and physics performance. The major design choices are described and the principle drivers for the direction of conceptual development, resulting in the operating space for EU-DEMO, are identified. The final output of the systems code forms the basis for more detailed engineering and physics evaluation and design work.}, language = {en}, - urldate = {2019-10-28}, - journal = {Journal of Nuclear Materials}, - author = {Zhang, Wei and Han, Han and Dai, Jianxing and Ren, Cuilan and Wang, Chengbin and Yan, Long and Huang, Hefei and Zhu, Zhiyuan}, + urldate = {2022-03-15}, + journal = {Fusion Engineering and Design}, + author = {Kembleton, R. and Morris, J. and Siccinio, M. and Maviglia, F.}, month = may, - year = {2019}, - keywords = {Bubble, Molecular Dynamics}, - pages = {48--53}, - file = {Zhang et al. - 2019 - Simulation of migration and coalescence of helium .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FRQTTC2L\\Zhang et al. - 2019 - Simulation of migration and coalescence of helium .pdf:application/pdf}, + year = {2022}, + keywords = {EU-DEMO, Physics and engineering basis, Reactor, Systems code}, + pages = {113080}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\I4JE54I8\\Kembleton et al. - 2022 - EU-DEMO design space exploration and design driver.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\D4VNH3JK\\S0920379622000801.html:text/html}, } -@article{buzi_response_2017, - title = {Response of tungsten surfaces to helium and hydrogen plasma exposure under {ITER} relevant steady state and repetitive transient conditions}, - volume = {57}, +@article{nguyen_developpement_nodate, + title = {Développement d'outils numériques pour la prise en compte du couplage hydrogène-plasticité dans un code éléments finis: application à l'essai de pliage en {U}}, + language = {fr}, + author = {Nguyen, Tuan Hung}, + pages = {165}, + file = {Nguyen - Développement d'outils numériques pour la prise en.pdf:D\:\\Logiciels\\data_zotero\\storage\\QN59NR8P\\Nguyen - Développement d'outils numériques pour la prise en.pdf:application/pdf}, +} + +@article{delaporte-mathurin_fuel_2021, + title = {Fuel retention in {WEST} and {ITER} divertors based on {FESTIM} monoblock simulations}, + volume = {61}, + copyright = {All rights reserved}, issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/aa81e4}, - doi = {10.1088/1741-4326/aa81e4}, - abstract = {The effect of helium (He) plasma exposure, and associated surface modifications, on the thermal shock resistance of tungsten (W) under ITER relevant steady state and transient heat and particle loads was studied. W samples were exposed to steady state and pulsed He plasmas at surface base temperatures from 670 to 1170 K. The same exposures were repeated in hydrogen (H) to allow a direct comparison of the role of the ion species on the thermal shock resistance. Exposure to He plasma pulses caused the formation of fine cracking network on W samples which occurred at a higher density and smaller depths compared to H pulsed plasma irradiation. The peak temperature reached during an ELM-like plasma pulse increased by a factor 1.45 over the 100 s of He plasma exposure, indicating a deterioration of the thermal properties. Transient loading experiments were also performed using a high power pulsed laser during He plasma exposure, showing a significant modification of the target thermal response caused by the surface damage. The effect of He-induced morphology changes on the thermal response modification was found to be very small compared to that of transient-induced damage.}, + url = {https://doi.org/10.1088/1741-4326/ac2bbd}, + doi = {10.1088/1741-4326/ac2bbd}, + abstract = {The influence of the input power (IP), puffing rate and neutral pressure on the fuel (hydrogen isotopes) inventory of the WEST and ITER divertors is investigated. For the chosen range of parameters (relatively low temperature at the strike points), the inventory of the WEST divertor evolves as the power 0.2 of the puffing rate and as the power 0.3 of the IP. The inventory at the strike points is highly dominated by ions whereas it is dominated by neutrals in the private zone. Increasing the fuelling rate increases the retention in the private zone and decreases slightly the retention at the strike points. Increasing the IP increases the inventory at the strike points and does not affect much the inventory at the private flux region. The inventory of the ITER divertor is not strongly dependent on the divertor neutral pressure. The inventory increases from 0 Pa to 7 Pa and then decreases slightly from 7 Pa to 10 Pa. After 107 s of continuous exposure, the maximum inventory in the ITER divertor was found to be 14 g. The inventory is not maximum at the strike points due to the high surface temperature of the monoblocks in this region. The maximum accumulation of H in the ITER divertor is below 5 mg per 400 s discharge and below 2 mg per 400 s discharge after 200 discharges.}, language = {en}, number = {12}, - urldate = {2019-10-07}, + urldate = {2022-02-24}, journal = {Nuclear Fusion}, - author = {Buzi, L. and Temmerman, G. De and Huisman, A. E. and Bardin, S. and Morgan, T. W. and Rasinski, M. and Pitts, R. A. and Oost, G. Van}, - month = sep, - year = {2017}, - keywords = {Experiment, Blistering}, - pages = {126009}, - file = {Buzi et al. - 2017 - Response of tungsten surfaces to helium and hydrog.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JJXGVR76\\Buzi et al. - 2017 - Response of tungsten surfaces to helium and hydrog.pdf:application/pdf}, + author = {Delaporte-Mathurin, Rémi and Yang, Hao and Denis, Julien and Dark, James and Hodille, Etienne A. and Temmerman, Gregory De and Bonnin, Xavier and Mougenot, Jonathan and Charles, Yann and Bufferand, Hugo and Ciraolo, Guido and Grisolia, Christian}, + month = oct, + year = {2021}, + note = {Publisher: IOP Publishing}, + pages = {126001}, + file = {Delaporte-Mathurin_2021_Nucl._Fusion_61_126001.pdf:D\:\\Logiciels\\data_zotero\\storage\\479BUFYN\\Delaporte-Mathurin_2021_Nucl._Fusion_61_126001.pdf:application/pdf}, } -@article{henriksson_molecular_2006, - title = {Molecular dynamics simulations of helium cluster formation in tungsten}, - volume = {244}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X05018288}, - doi = {10.1016/j.nimb.2005.10.020}, - abstract = {Molecular dynamics simulations of helium implantation into single-crystalline tungsten at 0 and 300K have been performed. Non-damaging ion energies of 50, 100 and 200eV were used. Clusters containing up to the order of 100 He atoms were formed. These clusters were nucleated athermally, via the creation of (111) crowdion interstitials and interstitial dislocation loop punching. Ruptures of He clusters were observed, but no associated ejection of W atoms.}, +@article{kremer_influence_2022, + title = {Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179122000242}, + doi = {10.1016/j.nme.2022.101137}, + abstract = {We studied the influence of thin, electro-chemically grown tungsten (W) surface oxide films on hydrogen isotope release from W. As deuterium (D) reservoir underneath the oxide, we used a defect-rich, ion-irradiated W layer that was filled with D prior to oxidation. Several oxide films with thicknesses between 5 and 100nm were studied and compared with tungsten with a natural oxide film. The release of D through the oxide film was analyzed with thermal desorption spectroscopy (TDS). The depth-resolved concentration profiles of D in the sample were measured with nuclear reaction analysis at all experimental steps. Changes of the morphology of the oxide film due to the release of D were investigated with scanning electron microscopy (SEM). In TDS studies, we found that the thin oxide films significantly influence the release behavior of D from W. The first D release peak (at 560K) is shifted towards higher temperature (or later times) with increasing oxide thickness. This indicates that the oxide film acts as both a D reservoir and a transport barrier that delays D release at temperatures above 475K. At this temperature, D also starts to interact chemically with the oxide film and is released not only as HD or D2 but also in the form of heavy water (HDO and D2O). Above 700K, D is released only in form of heavy water as long as enough oxide is available. Accordingly, SEM images after TDS show a strong modification of the oxide film. For film thicknesses of 5-10nm, all oxide is removed from the surface and smooth metallic W remains. For 15nm, the surface is still partially covered by oxide islands with several micrometer of metallic W between them. From the fact that D is still only released as heavy water at high temperatures, we conclude that the mobility of D atoms at the surface is very high. Even D atoms that surface far from an oxide island apparently travel along the surface to form an O-D group at the W oxide before they recombine with another D atom to form water. Our results indicate that the oxide film becomes relevant for the D release during TDS if the ratio of O atoms on the surface to D atoms in the sample is larger than 5-10 \%. Consequently, even the natural oxide film (1-2nm) that forms on W upon contact with air may significantly influence the D release spectra from TDS for experiments with low D retention.}, language = {en}, - number = {2}, - urldate = {2019-10-30}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Henriksson, K. O. E. and Nordlund, K. and Keinonen, J.}, - month = mar, - year = {2006}, - keywords = {Bubble, Molecular Dynamics, Bursting, Helium, Tungsten, Molecular dynamics simulations, Implantation, (100) Surface, Cluster}, - pages = {377--391}, - file = {Henriksson et al. - 2006 - Molecular dynamics simulations of helium cluster f.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X2RTJVQL\\Henriksson et al. - 2006 - Molecular dynamics simulations of helium cluster f.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PEDJTZ93\\S0168583X05018288.html:text/html}, + urldate = {2022-02-21}, + journal = {Nuclear Materials and Energy}, + author = {Kremer, K. and Brucker, M. and Jacob, W. and Schwarz-Selinger, T.}, + month = feb, + year = {2022}, + keywords = {D release from tungsten, deuterium release, hydrogen isotope release, Hydrogen Isotope retention, NRA, TDS, thin films, tungsten oxide, water formation}, + pages = {101137}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\78CIJ98Z\\S2352179122000242.html:text/html}, } -@article{hamid_molecular_2019, - title = {Molecular dynamics simulations of helium clustering and bubble growth under tungsten surfaces}, - volume = {163}, - issn = {0927-0256}, - url = {http://www.sciencedirect.com/science/article/pii/S0927025619301314}, - doi = {10.1016/j.commatsci.2019.03.008}, - abstract = {We study the surface response of W\{001\} to helium bombardment using molecular dynamics simulations. Simulations have been performed for incident helium of energy 80 eV and surface temperature 2100 K. The saturation of He retention has been observed to be high, a result of the bubbles trapping helium atoms and preventing them from diffusing to the surface and further back into the plasma. On the other hand, we have observe near-surface “cluster rupture” leading to the expulsion of helium atoms towards the vacuum. We have found that bubbles typically grow in a relatively narrow band of He/V ratios (1–3). Besides, it was observed that tungsten atoms migrated from the top surface into the bulk. The coalescence of helium bubbles has also been observed.}, - language = {en}, - urldate = {2019-10-28}, - journal = {Computational Materials Science}, - author = {Hamid, Ali Y. and Sun, Jizhong and Zhang, Hongyu and Jadon, Arvind S. and Stirner, Thomas}, - month = jun, - year = {2019}, - keywords = {Bubble, Molecular Dynamics}, - pages = {141--147}, - file = {Hamid et al. - 2019 - Molecular dynamics simulations of helium clusterin.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XGXTWNTR\\Hamid et al. - 2019 - Molecular dynamics simulations of helium clusterin.pdf:application/pdf}, -} - -@article{hu_interactions_2014, - title = {Interactions of mobile helium clusters with surfaces and grain boundaries of plasma-exposed tungsten}, - volume = {115}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.4874675}, - doi = {10.1063/1.4874675}, - abstract = {We report results of atomistic computations for the interactions of small mobile helium clusters (Hen) with free surfaces and grain boundaries (GBs) in tungsten toward development of continuum drift-diffusion-reaction models for the dynamics of mobile helium clusters in plasma-exposed tungsten. Molecular-statics (MS) simulations based on reliable many-body interatomic potentials are carried out for Hen (1 ≤ n ≤ 7) clusters near sinks to obtain the potential energy profiles of the Hen clusters as a function of the clusters' center-of-mass distance from a sink. Sinks investigated include surfaces, GBs, and regions in the vicinity of junctions where GBs intersect free surfaces. Elastic interaction potentials based on elastic inclusion theory provide an excellent description of the MS results for the cluster-sink interactions. The key parameter in the elastic models is the sink segregation strength, which is found to increase with increasing cluster size. Such cluster-sink interactions are responsible for the migration of small helium clusters by drift and for helium segregation on surfaces and grain boundaries in tungsten. Such helium segregation on sinks is observed in large-scale molecular-dynamics simulations of helium aggregation in model polycrystalline tungsten at 933 K upon helium implantation.}, - number = {17}, - urldate = {2019-10-31}, - journal = {Journal of Applied Physics}, - author = {Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, - month = may, - year = {2014}, - pages = {173512}, -} - -@article{woller_dynamic_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Dynamic measurement of the helium concentration of evolving tungsten nanostructures using {Elastic} {Recoil} {Detection} during plasma exposure}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514009337}, - doi = {10.1016/j.jnucmat.2014.11.126}, - abstract = {Helium (He) concentration depth profiles of evolving tungsten (W) nanostructures have been measured for the first time using in situ Elastic Recoil Detection (ERD) throughout plasma irradiation. Exposures resulting in fuzzy and non-fuzzy surfaces were analyzed in order to illuminate the role of He during the development of these surface morphologies. ERD was performed on samples with surface temperatures from Ts=530–1100K and irradiated by He flux densities of ΓHe∼1020–1022 m−2s−1. He concentration profiles in samples that developed either non-fuzzy or fuzzy surfaces are uniformly shaped with concentrations of 1.5–7at.\%, which is presumed to be too low for pressure driven growth models. Therefore, surface morphology changes are not perpetuated by continuous bubble bursting deformation. Also, a threshold in He flux density above 1020m−2s−1 is suggested by using in situ ERD to monitor the depth profile evolution of the He-rich layer while changing the flux during exposure.}, - language = {en}, - urldate = {2019-11-04}, - journal = {Journal of Nuclear Materials}, - author = {Woller, K. B. and Whyte, D. G. and Wright, G. M.}, - month = aug, - year = {2015}, - keywords = {Experiment, Fuzz}, - pages = {289--293}, - file = {Woller et al. - 2015 - Dynamic measurement of the helium concentration of.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MSD8287P\\Woller et al. - 2015 - Dynamic measurement of the helium concentration of.pdf:application/pdf}, -} - -@article{lemahieu_h/he_2016, - series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, - title = {H/{He} irradiation on tungsten exposed to {ELM}-like thermal shocks}, - volume = {109-111}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379616302319}, - doi = {10.1016/j.fusengdes.2016.03.035}, - abstract = {ELM-like thermal shocks and H/He particle exposure were subsequently applied on tungsten samples. Polished test specimens underwent in the JUDITH1 electron beam facility 100 transient thermal events with a duration of 1ms. The absorbed heat flux was 0.4GWm−2 and 1.5GWm−2, which is above the material's damage threshold. These experiments were done at room temperature and with the samples heated to 400°C base temperature. Depending on the loading conditions the test specimens have either a crack network or showed surface roughening. The samples were then loaded in the GLADIS facility at different surface temperatures with a mixed H/He beam with a flux of 3.7×1021m−2s−1. Post-mortem analysis showed that the roughened surface did not alter the H/He induced surface modifications. In contrast to that on the test specimens that exhibited crack formation, phenomena such as bubble creation along the crack edge, formation of a shallow layer of nano-structures covering the crack opening, and the emerging of a porous structure which partially fills the crack are observed.}, - language = {en}, - urldate = {2019-11-04}, - journal = {Fusion Engineering and Design}, - author = {Lemahieu, Nathan and Balden, Martin and Elgeti, Stefan and Greuner, Henri and Linke, Jochen and Maier, Hans and Pintsuk, Gerald and Wirtz, Marius and Van Oost, Guido and Noterdaeme, Jean-Marie}, - month = nov, - year = {2016}, - keywords = {Bubble, Experiment, Fuzz}, - pages = {169--174}, - file = {Lemahieu et al. - 2016 - HHe irradiation on tungsten exposed to ELM-like t.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D3M39Z9C\\Lemahieu et al. - 2016 - HHe irradiation on tungsten exposed to ELM-like t.pdf:application/pdf}, -} - -@article{markelj_hydrogen_2017, - title = {Hydrogen isotope accumulation in the helium implantation zone in tungsten}, - volume = {57}, - issn = {0029-5515}, - doi = {10.1088/1741-4326/aa6b27}, - abstract = {The influence of helium (He) on deuterium (D) transport and retention was studied experimentally in tungsten (W). Helium was implanted 1 µm deep into W to a maximum calculated concentration of 3.4 at.\%. To minimize the influence of displacement damage created during the He implantation on D retention, so-called self-damaged W was used. W was damaged by 20 MeV W ion bombardment and defects were populated by low-temperature D plasma at room temperature before He implantation. Deuterium depth profiling was performed in situ during isochronal annealing in the temperature range from 300 K to 800 K. It is shown for the first time unambiguously that He attracts D and locally increases D trapping. Deuterium retention increased by a factor of two as compared to a non-He implanted W reference after sample annealing at 450 K. Rate equation modelling can explain the measured D depth profiles quantitatively when keeping the de-trapping parameters unchanged but only increasing the number of traps in the He zone. This bolsters the confidence in the theoretical calculations predicting that more hydrogen isotopes can be stored around a He cluster zone.}, - language = {en}, - number = {6}, - journal = {Nuclear Fusion}, - author = {Markelj, S. and Schwarz-Selinger, T. and Založnik, A.}, - month = apr, - year = {2017}, - keywords = {Experiment, Macroscopic rate equations}, - pages = {064002}, - file = {Markelj et al. - 2017 - Hydrogen isotope accumulation in the helium implan.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3HY5B9GZ\\Markelj et al. - 2017 - Hydrogen isotope accumulation in the helium implan.pdf:application/pdf}, -} - -@article{miyamoto_systematic_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Systematic investigation of the formation behavior of helium bubbles in tungsten}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514009131}, - doi = {10.1016/j.jnucmat.2014.10.098}, - abstract = {The formation of He bubbles in tungsten under exposure to a He plasma was systematically investigated using low energy (∼50eV) He+ ions with a wide fluence range (∼1023 to 1026m−2) in the linear divertor plasma simulator PISCES-A at several temperatures (523–973K). TEM observations after thinning exposed W samples with FIB revealed that the layer thickness ({\textgreater}30nm) of He bubbles largely exceeds the ion implantation range of a few nm. The size of He bubbles was found to increase with an increase in the sample temperature: it was around 10nm at 973K, while only small He bubbles of 1–2nm were observed at {\textless}773K. In addition, to obtain information on the initial formation behavior, in-situ TEM observations during He ion irradiation were also performed.}, - language = {en}, - urldate = {2019-10-25}, - journal = {Journal of Nuclear Materials}, - author = {Miyamoto, M. and Mikami, S. and Nagashima, H. and Iijima, N. and Nishijima, D. and Doerner, R. P. and Yoshida, N. and Watanabe, H. and Ueda, Y. and Sagara, A.}, - month = aug, - year = {2015}, - keywords = {Bubble, Experiment}, - pages = {333--336}, - file = {Miyamoto et al. - 2015 - Systematic investigation of the formation behavior.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A2NYSRF4\\Miyamoto et al. - 2015 - Systematic investigation of the formation behavior.pdf:application/pdf}, -} - -@article{nishijima_sputtering_2011, - series = {Proceedings of the 19th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion}}, - title = {Sputtering properties of tungsten ‘fuzzy’ surfaces}, - volume = {415}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S002231151000838X}, - doi = {10.1016/j.jnucmat.2010.12.017}, - abstract = {Sputtering yields of He-induced W ‘fuzzy’ surfaces bombarded by Ar have been measured in the linear divertor plasma simulator PISCES-B. It is found that the sputtering yield of a fuzzy surface, Yfuzzy, decreases with increasing fuzzy layer thickness, L, and saturates at ∼10\% of that of a smooth surface, Ysmooth, at L{\textgreater}1μm. The reduction in the sputtering yield is suspected to be due mainly to the porous structure of fuzz, since the ratio, Yfuzzy/Ysmooth follows (1−pfuzz), where pfuzz is the fuzz porosity. Further, Yfuzzy/Ysmooth is observed to increase with incident ion energy, Ei. This may be explained by an energy dependent change in the angular distribution of sputtered W atoms, since at lower Ei, the angular distribution is observed to become more butterfly-shaped. That is, a larger fraction of sputtered W atoms can line-of-sight deposit/stick onto neighboring fuzz nanostructures for lower Ei butterfly distributions, resulting in lower ratio of Yfuzzy/Ysmooth.}, - language = {en}, - number = {1, Supplement}, - urldate = {2019-11-04}, - journal = {Journal of Nuclear Materials}, - author = {Nishijima, D. and Baldwin, M. J. and Doerner, R. P. and Yu, J. H.}, - month = aug, - year = {2011}, - keywords = {Experiment, Fuzz}, - pages = {S96--S99}, - file = {Nishijima et al. - 2011 - Sputtering properties of tungsten ‘fuzzy’ surfaces.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\STJ448CU\\Nishijima et al. - 2011 - Sputtering properties of tungsten ‘fuzzy’ surfaces.pdf:application/pdf}, -} - -@article{baldwin_helium_2008, - title = {Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions}, - volume = {48}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/48/3/035001}, - doi = {10.1088/0029-5515/48/3/035001}, - abstract = {Polished W discs exposed to pure He plasma in the PISCES-B linear-divertor-plasma simulator at 1120 and 1320 K are found to develop deeply nanostructured surface layers consisting of a conglomerate of amorphous ‘nanorods’. The growth of the thickness of the nanostructured layer is explored for exposure times spanning 300–(2.2 × 104) s in He plasmas of density ne ∼ 4 × 1018 m−3 and temperature Te ∼ 6–8 eV where the average He-ion surface-impact energy is ∼60 eV, below the threshold for physical sputtering. A nanostructured layer in excess of 5 µm thick is observed for the longest exposure time explored. The kinetics of the layer growth are found to follow Fick's law, characterized by an effective diffusive mechanism with coefficients of diffusion: D1120 K = 6.6 ± 0.4 × 10−12 cm2 s−1 and D1320 K = 2.0± 0.5 × 10−11 cm2 s−1. The diffusion of He atoms in W is considered too rapid to explain the observed growth of surface modification and points to the interplay of other mechanisms, such as the availability of thermal vacancies and/or the slower diffusion of He through the forming nanostructured layer.}, +@article{utili_design_2022, + title = {Design of the {Test} {Section} for the {Experimental} {Validation} of {Antipermeation} and {Corrosion} {Barriers} for {WCLL} {BB}}, + volume = {12}, + copyright = {http://creativecommons.org/licenses/by/3.0/}, + issn = {2076-3417}, + url = {https://www.mdpi.com/2076-3417/12/3/1624}, + doi = {10.3390/app12031624}, + abstract = {Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction. Several technologies were investigated as antipermeation and corrosion barriers to reduce the tritium permeation flux from the breeder into the PHTS. Within this frame, alumina coating manufactured by Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) are two of the main candidates for the Water Cooled Lithium Lead (WCLL) Breeder Blanket (BB). In order to validate the performance of the coatings on relevant WCLL BB geometries, a mock-up was designed and will be characterized in an experimental facility operating with flowing lithium-lead, called TRIEX-II. The present work aims to illustrate the preliminary engineering design of a WCLL BB mock-up in order to deeply investigate permeation of hydrogen isotopes through PHTS water pipes. The permeation tests are planned in the temperature range between 330 and 500 °C, with hydrogen and deuterium partial pressure in the range of 1–1000 Pa. The hydrogen isotopes transport analysis carried out for the design and integration of the mock-up in TRIEX-II facility is also shown.}, language = {en}, number = {3}, - urldate = {2019-10-30}, - journal = {Nuclear Fusion}, - author = {Baldwin, M. J. and Doerner, R. P.}, + urldate = {2022-02-15}, + journal = {Applied Sciences}, + author = {Utili, Marco and Alberghi, Ciro and Candido, Luigi and Di Fonzo, Fabio and Papa, Francesca and Venturini, Alessandro}, month = jan, - year = {2008}, - keywords = {Experiment, Fuzz}, - pages = {035001}, - file = {Baldwin et Doerner - 2008 - Helium induced nanoscopic morphology on tungsten u.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FJEPVE75\\Baldwin et Doerner - 2008 - Helium induced nanoscopic morphology on tungsten u.pdf:application/pdf}, -} - -@article{takamura_formation_2006, - title = {Formation of {Nanostructured} {Tungsten} with {Arborescent} {Shape} due to {Helium} {Plasma} {Irradiation}}, - volume = {1}, - doi = {10.1585/pfr.1.051}, - abstract = {Deeply nanostructured tungsten with an arborescent shape was found for the first time to be formed on tungsten-coated graphite by a high-flux helium plasma irradiation at surface temperatures of 1250 and 1600 K, an incident ion energy of 12 eV (well below the physical sputtering threshold) and a helium ion fluence of 3.5 × 1027 m-2.}, - journal = {Plasma and Fusion Research}, - author = {Takamura, Shuichi and Ohno, Noriyasu and Nishijima, Dai and Kajita, Shin}, - year = {2006}, - keywords = {Experiment, Fuzz}, - pages = {051--051}, - file = {Takamura et al. - 2006 - Formation of Nanostructured Tungsten with Arboresc.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SP9UEUI4\\Takamura et al. - 2006 - Formation of Nanostructured Tungsten with Arboresc.pdf:application/pdf}, -} - -@article{baldwin_formation_2010, - title = {Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades}, - volume = {404}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311510002849}, - doi = {10.1016/j.jnucmat.2010.06.034}, - abstract = {The response of a variety of W material grades to nanostructure ‘fuzz’ formation is explored. W targets are exposed to He or D2–0.2He plasmas in PISCES-B at 900–1320K to below sputter threshold He+ ions of energy 25–60eV for up to 2.2×104s. SEM and XPS reveal nanoscopic reorganization of the W surface to a layer of ‘fuzz’ of porosity ∼90\% as determined by a ‘fuzz’ removal/weight loss method. The variability of ‘fuzz’ growth is examined at 1120K for 1h durations: SR, SC and doped W grades – La2O3 (1\% wt.), Re (5\% and 10\% wt.), and TiC (1.5\% wt.) developed 2–3μm thick ‘fuzz’ layers, while a VPS grade developed a layer 4μm thick. An RC grade revealed additional ‘fuzz’ at deep ({\textgreater}100μm) grain boundaries. However, heat treatment up to 1900K produced reintegration of ‘fuzz’ with the bulk and He release at ∼1000K and ∼1400–1800K due to depopulation from vacancy complexes.}, - language = {en}, - number = {3}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Baldwin, M. J. and Doerner, R. P.}, - month = sep, - year = {2010}, - keywords = {Experiment, Fuzz}, - pages = {165--173}, - file = {Baldwin et Doerner - 2010 - Formation of helium induced nanostructure ‘fuzz’ o.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X84YDP2C\\Baldwin et Doerner - 2010 - Formation of helium induced nanostructure ‘fuzz’ o.pdf:application/pdf}, + year = {2022}, + note = {Number: 3 +Publisher: Multidisciplinary Digital Publishing Institute}, + keywords = {antipermeation barrier, corrosion barrier, DEMO, ITER, lithium-lead, WCLL}, + pages = {1624}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2FD3KPJT\\Utili et al. - 2022 - Design of the Test Section for the Experimental Va.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EW8UW2HZ\\1624.html:text/html}, } -@article{wright_tungsten_2012, - title = {Tungsten nano-tendril growth in the {Alcator} {C}-{Mod} divertor}, - volume = {52}, +@article{bae_arc_2022, + title = {{ARC} reactor neutronics multi-code validation}, issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/52/4/042003}, - doi = {10.1088/0029-5515/52/4/042003}, - abstract = {Growth of tungsten nano-tendrils (‘fuzz’) has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14 consecutive helium L-mode discharges in Alcator C-Mod, the tip of a tungsten Langmuir probe at the outer strike point was fully covered with a layer of nano-tendrils. The thickness of the individual nano-tendrils (50–100 nm) and the depth of the layer (600 ± 150 nm) are consistent with observations from experiments on linear plasma devices. The observation of tungsten fuzz in a tokamak may have important implications for material erosion, dust formation, divertor lifetime and tokamak operations in next-step devices.}, + url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac536a}, + doi = {10.1088/1741-4326/ac536a}, + abstract = {The affordable, robust, compact (ARC) reactor is a tokamak fusion reactor concept currently under development by Commonwealth Fusion Systems (CFS)and Massachusetts Institute of Technology. There are three important neutronics considerations for the operation of the ARC reactor: (1) breeding of enough tritium in the blanket to sustain the D-T reaction in the plasma; (2) ensuring low fluence on the superconducting toroidal field coils; and (3) assessing neutron volumetric heating in structural components. This work aims to perform a validation of the neutronics analysis approach by code-to-code comparison. State-of-the-art software stacks are employed for the neutronics analysis of the ARC reactor, and a computer-aided design (CAD) model is used directly for Monte Carlo (MC) neutron transport calculations. Three software stacks, Attila-MCNP, OpenMC-DAGMC, and Shift-DAGMC, are used to perform neutronic analysesof a 90°sector CAD model of the ARC reactor. Results show that the flux tallies calculated by the three software stacks are very close. Also, the volumetric heatingand tritium breeding values have less than 0.6\% relative difference between codes.}, language = {en}, - number = {4}, - urldate = {2019-10-30}, + urldate = {2022-02-10}, journal = {Nuclear Fusion}, - author = {Wright, G. M. and Brunner, D. and Baldwin, M. J. and Doerner, R. P. and Labombard, B. and Lipschultz, B. and Terry, J. L. and Whyte, D. G.}, - month = mar, - year = {2012}, - keywords = {Experiment, Fuzz}, - pages = {042003}, - file = {Wright et al. - 2012 - Tungsten nano-tendril growth in the Alcator C-Mod .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZCEK7C3P\\Wright et al. - 2012 - Tungsten nano-tendril growth in the Alcator C-Mod .pdf:application/pdf}, -} - -@article{cui_thermal_2017, - title = {Thermal conductivity reduction of tungsten plasma facing material due to helium plasma irradiation in {PISCES} using the improved 3-omega method}, - volume = {486}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311516303488}, - doi = {10.1016/j.jnucmat.2017.01.023}, - abstract = {The near-surface region of plasma facing material (PFM) plays an important role in thermal management of fusion reactors. In this work, we measured thermal conductivity of tungsten (W) surface layers damaged by He plasma in PISCES at UCSD. We studied the damage effect on both bulk, and thin film, W. We observed that the surface morphology of both bulk and thin film was altered after exposure to He plasma with the fluence of 1 × 1026 m−2 (bulk) and 2 × 1024 m−2 (thin film). Transmission electron microscopy (TEM) analysis reveals that the depth of the irradiation damaged layer was approximately 20 nm on the bulk W exposed to He plasma at 773 K for 2000 s. In order to measure the thermal conductivity of this exceedingly thin damaged layer in the bulk W, we adopted the well-established ‘3-omega’ method and employed novel nanofabrication techniques to improve the measurement sensitivity. For the damaged W thin film sample, we measured the reduction in electrical conductivity and used the Wiedemann-Franz (W-F) law to extract the thermal conductivity. Results from both measurements show that thermal conductivity in the damaged layers was reduced by at least ∼80\% compared to that of undamaged W. This large reduction in thermal conductivity can be attributed to the scattering of electrons, the dominant heat carriers in W, caused by defects introduced by He plasma irradiation.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Cui, Shuang and Simmonds, Michael and Qin, Wenjing and Ren, Feng and Tynan, George R. and Doerner, Russell P. and Chen, Renkun}, - month = apr, - year = {2017}, - keywords = {Experiment}, - pages = {267--273}, - file = {Cui et al. - 2017 - Thermal conductivity reduction of tungsten plasma .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JXBSAZE6\\Cui et al. - 2017 - Thermal conductivity reduction of tungsten plasma .pdf:application/pdf}, -} - -@article{tokunaga_synergistic_2004, - series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)}, - title = {Synergistic effects of high heat loading and helium irradiation of tungsten}, - volume = {329-333}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311504003149}, - doi = {10.1016/j.jnucmat.2004.04.178}, - abstract = {High heat flux experiments using a helium beam have been carried out on powder metallurgy tungsten. The energy of He is 19 keV. He beam flux and heat flux at the beam center is 2.0×1021 He/m2s and 6.0 MW/m2, respectively. Beam duration is 3.0–3.9 s and interval of beam shot start is 30 s. The samples are irradiated up to a fluence of 1022–1024 He/m2 by the repeated irradiation pulses. In addition to the He beam irradiation, high heat flux experiments using hydrogen and electron beams have also been carried out on the samples. After the irradiation, surface modification by the irradiation has been investigated. Surface modification by helium and hydrogen beams is completely different from results of electron beam heating. In particular, helium beam heating causes remarkably surface modification such as a fine-scale rough surface at a peak temperature above 2400 °C.}, - language = {en}, - urldate = {2019-11-04}, - journal = {Journal of Nuclear Materials}, - author = {Tokunaga, K and Tamura, S and Yoshida, N and Ezato, K and Taniguchi, M and Sato, K and Suzuki, S and Akiba, M}, - month = aug, - year = {2004}, - keywords = {Experiment, Blistering}, - pages = {757--760}, - file = {Tokunaga et al. - 2004 - Synergistic effects of high heat loading and heliu.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2GRVRL38\\Tokunaga et al. - 2004 - Synergistic effects of high heat loading and heliu.pdf:application/pdf}, -} - -@article{singh_nucleation_1984, - title = {Nucleation of helium bubbles on dislocations, dislocation networks and dislocations in grain boundaries during 600 {MeV} proton irradiation of aluminium}, - volume = {125}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/0022311584905567}, - doi = {10.1016/0022-3115(84)90556-7}, - abstract = {High-purity aluminium (99.9999\%) was irradiated with 600 MeV protons with a damage rate of 3.5 × 10−6dpa/s. Irradiation with 600 MeV protons produces helium and hydrogen at the rate of 140 and 615 appm per dpa, respectively. Specimens irradiated at temperatures in the range 116 to 318 °C to doses in the range 0.04 to 5 dpa were examined in a transmission electron microscope (TEM). The TEM investigation has shown that helium bubbles are formed on dislocations in the grains as well as dislocations in the grain boundaries. Dislocation nodal points whether present in dislocation walls or in grain boundaries are found to be the most favourable sites for bubble nucleation. The mean diameter of the bubbles on individual dislocation lines are found to be larger than those for the bubbles in the matrix. The bubble size and density on grain boundaries vary from boundary to boundary. The size of these bubbles on the boundaries is larger than or equal to the size of those in the matrix. It is suggested that helium atoms once arrived at a dislocation remain bound to the dislocation line but at the same time remain mobile within the dislocation core; the bubble nucleation behaviour in the core would thus be affected by the core structure of the different dislocations. An estimate of the effective helium diffusion in the dislocations relative to that in the lattice has been made on the basis of the measured bubble parameters and the width of the bubble-denuded zone along dislocation lines; the diffusion coefficient of helium in the dislocations is found to be about the same as that in the lattice.}, - language = {en}, - number = {3}, - urldate = {2019-10-31}, - journal = {Journal of Nuclear Materials}, - author = {Singh, B. N. and Leffers, T. and Green, W. V. and Victoria, M.}, - month = aug, - year = {1984}, - keywords = {Bubble, Experiment}, - pages = {287--297}, - file = {Singh et al. - 1984 - Nucleation of helium bubbles on dislocations, disl.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NJWFEPJY\\Singh et al. - 1984 - Nucleation of helium bubbles on dislocations, disl.pdf:application/pdf}, -} - -@article{qin_helium_2019, - title = {Helium bubble nucleation at grain boundaries and its influence on intergranular fracture}, - volume = {99}, - issn = {1478-6435}, - url = {https://doi.org/10.1080/14786435.2018.1551634}, - doi = {10.1080/14786435.2018.1551634}, - abstract = {An in-depth understanding of the formation of intergranular helium bubbles and its relation to embrittlement is an important issue in the nuclear industry. In this paper, a thermodynamic model is developed to analyze the nucleation of intergranular helium bubbles. Microstructural observation using scanning electron microscopy and electron backscatter diffraction gives a detailed description for the relation between the bubble formation and the grain-boundary (GB) misorientation in helium-implanted nickel and Inconel X750. The theoretical and the experimental results confirm that the nucleation of intergranular helium bubbles is GB structure-dependent, the helium-to-vacancy ratio plays an important role in the bubble precipitation, and the interfacial tension of bubbles cannot be approximated to be the interfacial energy. The bubble-induced intergranular embrittlement in a polycrystal is modelled. The GB misorientation distribution, the intergranular bubble nucleation and growth and the GB connectivity are the key factors affecting the GB fracture toughness. The hoop ductility of the cladding tubes containing helium is analyzed. The hoop stress-induced increase in the GB energy promotes the precipitation of bubbles at the radial GBs and lead to the loss of tube ductility. Based on this work, the complicated correlation among the intergranular helium bubbles, the GB structure, the helium concentration, the applied stress and the helium embrittlement is clarified.}, - number = {6}, - urldate = {2019-10-31}, - journal = {Philosophical Magazine}, - author = {Qin, W. and Chauhan, A. K. and Szpunar, J. A.}, - month = mar, - year = {2019}, - keywords = {Bubble, Experiment}, - pages = {679--698}, -} - -@article{taylor_investigating_2019, - title = {Investigating {Helium} {Bubble} {Nucleation} and {Growth} through {Simultaneous} {In}-{Situ} {Cryogenic}, {Ion} {Implantation}, and {Environmental} {Transmission} {Electron} {Microscopy}}, - volume = {12}, - issn = {1996-1944}, - url = {https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6719068/}, - doi = {10.3390/ma12162618}, - abstract = {Palladium can readily dissociate molecular hydrogen at its surface, and rapidly accept it onto the octahedral sites of its face-centered cubic crystal structure. This can include radioactive tritium. As tritium β-decays with a half-life of 12.3 years, He-3 is generated in the metal lattice, causing significant degradation of the material. Helium bubble evolution at high concentrations can result in blister formation or exfoliation and must therefore be well understood to predict the longevity of materials that absorb tritium. A hydrogen over-pressure must be applied to palladium hydride to prevent hydrogen from desorbing from the metal, making it difficult to study tritium in palladium by methods that involve vacuum, such as electron microscopy. Recent improvements in in-situ ion implantation Transmission Electron Microscopy (TEM) allow for the direct observation of He bubble nucleation and growth in materials. In this work, we present results from preliminary experiments using the new ion implantation Environmental TEM (ETEM) at the University of Huddersfield to observe He bubble nucleation and growth, in-situ, in palladium at cryogenic temperatures in a hydrogen environment. After the initial nucleation phase, bubble diameter remained constant throughout the implantation, but bubble density increased with implantation time. β-phase palladium hydride was not observed to form during the experiments, likely indicating that the cryogenic implantation temperature played a dominating role in the bubble nucleation and growth behavior.}, - number = {16}, - urldate = {2019-10-31}, - journal = {Materials}, - author = {Taylor, Caitlin A. and Briggs, Samuel and Greaves, Graeme and Monterrosa, Anthony and Aradi, Emily and Sugar, Joshua D. and Robinson, David B. and Hattar, Khalid and Hinks, Jonathan A.}, - month = aug, - year = {2019}, - pmid = {31426387}, - pmcid = {PMC6719068}, - keywords = {Bubble, Experiment}, - file = {Taylor et al. - 2019 - Investigating Helium Bubble Nucleation and Growth .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YM8TQXXI\\Taylor et al. - 2019 - Investigating Helium Bubble Nucleation and Growth .pdf:application/pdf}, -} - -@article{kornelsen_interaction_1972, - title = {The interaction of injected helium with lattice defects in a tungsten crystal}, - volume = {13}, - issn = {0033-7579}, - url = {https://doi.org/10.1080/00337577208231184}, - doi = {10.1080/00337577208231184}, - abstract = {Helium injected into tungsten has been found to undergo rapid interstitial diffusion at room temperature unless it encounters lattice defects. This effect has been used in a study of the lattice damage produced near a (100) tungsten surface by the impact of small numbers of 5 keV heavy ions. The helium, injected as 250eV ions, does not itself produce any observable damage, but is trapped in that created by the prior heavy ion bombardment. Thermal desorption spectra obtained by raising the crystal temperature at 40°K/sec show that the helium is bound with several discrete energies. Attempts to correlate the binding states with particular lattice defects have been made by varying the damage anneal temperature, the helium dose, the helium injection temperature and the mass of the damaging ion. The results suggest that all of the entrapment occurs at defects of the vacancy type, and that the binding energy is modified by parameters that change the available vacancy volume. In particular there is evidence that at least two and possibly three helium atoms can be trapped in a single vacancy, that two types of divacancies exist, and that vacancies become trapped in the strain field of large impurity atoms. It also appears that at sufficiently high helium doses ({\textgreater} 1014 ions/ cm2), any of the trapping sites can act as nuclei for the formation of helium bubbles.}, - number = {3-4}, - urldate = {2019-10-25}, - journal = {Radiation Effects}, - author = {Kornelsen, E. V.}, - month = apr, - year = {1972}, - keywords = {Bubble, Experiment}, - pages = {227--236}, - file = {Kornelsen - 1972 - The interaction of injected helium with lattice de.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZKHTEVL3\\Kornelsen - 1972 - The interaction of injected helium with lattice de.pdf:application/pdf}, -} - -@article{qu_degradation_2018, - title = {Degradation of thermal conductivity of the damaged layer of tungsten irradiated by helium-plasma}, - volume = {137}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618306045}, - doi = {10.1016/j.fusengdes.2018.08.014}, - abstract = {Pure tungsten samples were irradiated by helium plasma in the linear plasma device PSI-2 with an ion energy of 40 eV and a flux of 1.1 × 1022 m−2s−1. The irradiation temperature was from 523 K to 773 K and the fluence was from 1.0 × 1025 to 1.0 × 1026 m−2. A damaged layer of 10 nm thickness was formed on the sample surface with a destroyed crystalline structure. Helium-bubbles and surface modification in nanoscale were observed. Thermal conductivities of the ultra-thin damaged layers were measured by the transient thermoreflectance technique. Result shows that the thermal conductivity reduced two orders of magnitude compared to the bulk value and decreased with increasing irradiation temperature and fluence. Moreover, the helium-irradiated samples were exposed to ELM-like heat load produced by electron beam on EMS-60. The pulse length was 1 ms and each sample was exposed to 5 pulses. Melting occurred under power density of 1.7 GW m−2. As the thermal conductivity of the damaged layer decreased, the molten bath of the irradiated sample deepened. The degraded thermal conductivity led to a lower melting threshold. The characterization of the thermal conductivity of the damaged layer induced by the plasma irradiation is a promising way to estimate the damage level, as well as the failure threshold, of the plasma facing components.}, - urldate = {2019-10-07}, - journal = {Fusion Engineering and Design}, - author = {Qu, Shilian and Sun, Hao and Kreter, Arkadi and Yuan, Yue and Cheng, Long and Huang, Zhengxing and Xu, Ben and Chen, Wanqi and Cui, Wei and Tang, Zhenan and Jia, Yuzhen and Lian, YouYun and Liu, Xiang and Liu, Wei}, - month = dec, - year = {2018}, - keywords = {Experiment}, - pages = {97--103}, - file = {Qu et al. - 2018 - Degradation of thermal conductivity of the damaged.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NSNCFPG4\\Qu et al. - 2018 - Degradation of thermal conductivity of the damaged.pdf:application/pdf}, + author = {Bae, Jin Whan and Peterson, Ethan and Shimwell, Jonathan}, + year = {2022}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2AGWQXW7\\Bae et al. - 2022 - ARC reactor neutronics multi-code validation.pdf:application/pdf}, } -@phdthesis{sefta_surface_2013, - title = {Surface {Response} of {Tungsten} to {Helium} and {Hydrogen} {Plasma} {Flux} as a {Function} of {Temperature} and {Incident} {Kinetic} {Energy}}, - url = {https://escholarship.org/uc/item/0kw3r768}, - abstract = {Tungsten is a leading candidate material for the diverter in future nuclear fusion reactors. Previous experiments have demonstrated that surface defects and bubbles form in tungsten when ex- posed to helium and hydrogen plasmas, even at modest ion energies. In some regimes, between 1000K and 2000K, and for He energies below 100eV, "fuzz" like features form. The mechanisms leading to these surfaces comprised of nanometer sized tungsten tendrils which include visible helium bubbles are not currently known. The role of helium bubble formation in tendril morphology could very likely be the starting point of these mechanisms. Using Molecular dynamics (MD) simulations, the role of helium and hydrogen exposure in the initial formation mechanisms of tungsten "fuzz" are investigated. Molecular dynamics simulations are well suited to describe the time and length scales associated with initial formation of helium clusters that eventually grow to nano-meter sized helium bubbles. MD simulations also easily enable the modeling of a variety of surfaces such as single crystals, grain boundaries or "tendrils".While the sputtering yield of tungsten is generally low, previous observations of surface modification due to plasma exposure raise questions about the effects of surface morphology and sub-surface helium bubble populations on the sputtering behavior. Results of computational molecular dynamics are reported that investigate the influence of sub-surface helium bubble distributions on the sputtering yield of tungsten (100) and (110) surfaces induced by helium ion exposure in the range of 300 eV to 1 keV. The calculated sputtering yields are in reasonable agreement with a wide range of experimental data; but do not show any significant variation as a result of the pre-existing helium bubbles.Molecular dynamics simulations reveal a number of sub-surface mechanisms leading to nanometer- sized "fuzz" in tungsten exposed to low-energy helium plasmas. We find that during the bubble formation process, helium clusters create self-interstitial defect clusters in tungsten by a trap mutation process, followed by the migration of these defects to the surface that leads to the formation of layers of adatom islands on the tungsten surface. As the helium clusters grow into nanometer sized bubbles, their proximity to the surface and extremely high gas pressures can cause them to rupture the surface thus enabling helium release. Helium bubble bursting induces additional surface damage and tungsten mass loss which varies depending on the nature of the surface. We then show tendril-like geometries have surfaces that are more resilient to helium clustering and bubble formation and rupture. Finally, the study includes hydrogen to reveal the effect of a mixed 90\%H-10\%He plasma mix on the tungsten surface. We find that hydrogen greatly affects the tungsten surface, with a near surface hydrogen saturation layer, and that helium clusters still form and are attractive trapping sites for hydrogen.Molecular dynamics simulations have also investigated the effect of sub-surface helium bubble evolution on tungsten surface morphology. The helium bubble/tungsten surface interaction has been systematically studied to determine how parameters such as bubble shape and size, temperature, tungsten surface orientation and ligament thickness above the bubble impact bubble stability and surface evolution. The tungsten surface is roughened by a combination of adatom islands, craters and pinholes. The study provides insight into the mechanisms and conditions leading to various tungsten topology changes, most notably the formation of nanoscale fuzz.An atomistic study of the mechanisms behind initial phases of tungsten nano-fuzz growth has determined that tungsten surfaces are affected by sub-displacement energy helium and hydrogen fluxes through a series of mechanisms. Sub-surface helium atom clustering, bubble nucleation, growth and rupture lead to tungsten surface deformation. Helium clustering processes vary near grain boundaries or in tendril-like surface geometries. In the presence of hydrogen, these mechanisms are coupled with hydrogen surface saturation. Finally, further investigation to connect these atomistic mechanisms to nano-size tungsten fuzz growth is needed to get a comprehensive under- standing of the effects of low energy helium and hydrogen on tungsten.}, +@article{yamanishi_hydrogen_1983, + title = {Hydrogen {Permeation} and {Diffusion} through {Pure} {Fe}, {Pure} {Ni} and {Fe}\–{Ni} {Alloys}}, + volume = {24}, + issn = {0021-4434, 2432-4701}, + url = {https://www.jstage.jst.go.jp/article/matertrans1960/24/1/24_1_49/_article}, + doi = {10.2320/matertrans1960.24.49}, language = {en}, - urldate = {2019-10-28}, - school = {UC Berkeley}, - author = {Sefta, Faiza}, - year = {2013}, - keywords = {Bubble, Molecular Dynamics, Blistering, Bursting}, - file = {Sefta - 2013 - Surface Response of Tungsten to Helium and Hydroge.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DWFJ9TGD\\Sefta - 2013 - Surface Response of Tungsten to Helium and Hydroge.pdf:application/pdf}, + number = {1}, + urldate = {2022-02-05}, + journal = {Transactions of the Japan Institute of Metals}, + author = {Yamanishi, Y. and Tanabe, T. and Imoto, S.}, + year = {1983}, + pages = {49--58}, + file = {Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:D\:\\Logiciels\\data_zotero\\storage\\NPA6U8EC\\Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:application/pdf;Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:D\:\\Logiciels\\data_zotero\\storage\\32XPKFQ9\\Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:application/pdf}, } -@article{hu_dynamics_2014, - title = {Dynamics of small mobile helium clusters near tungsten surfaces}, - volume = {626}, - issn = {0039-6028}, - url = {http://www.sciencedirect.com/science/article/pii/S0039602814000867}, - doi = {10.1016/j.susc.2014.03.020}, - abstract = {We report the results of a systematic atomic-scale analysis of the dynamics of small mobile helium clusters in tungsten, near tungsten surfaces. These helium clusters are attracted to tungsten surfaces due to an elastic interaction force that drives surface segregation. As the clusters migrate toward the surface, trap mutation and cluster dissociation are activated at rates higher than in the bulk. These kinetic processes are responsible for important structural, morphological, and compositional features in plasma-exposed tungsten, including surface adatoms, near-surface immobile helium–vacancy complexes, and retained helium content. Detailed results are presented for di-helium and tri-helium clusters near low-Miller-index tungsten surfaces.}, +@techreport{san_marchi_technical_2012, + title = {Technical reference for hydrogen compatibility of materials.}, + url = {https://www.osti.gov/servlets/purl/1055634/}, + abstract = {The Technical Reference for Hydrogen Compatibility of Materials summarizes materials data related to hydrogen-assisted fracture (also called hydrogen embrittlement) in gaseous hydrogen environments, with emphasis on hydrogen permeation and structural properties. The Technical Reference generally does not provide specific recommendations for materials selection as the suitability of a given material depends on service conditions, in particular the mechanical and environmental conditions associated with a particular component, as well as the details of the materials microstructure. In substance, the Technical Reference is a collection of stand-alone documents organized by materials class, which have been compiled into this composite report. The individual sections are occasionally updated and new sections are added; the most recent versions are available from our website at http://www.ca.sandia.gov/matlsTechRef/. This compilation updates the previous composite release: SAND2008-1163.}, language = {en}, - urldate = {2019-10-28}, - journal = {Surface Science}, - author = {Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, - month = aug, - year = {2014}, - keywords = {Molecular Dynamics}, - pages = {L21--L25}, - file = {Hu et al. - 2014 - Dynamics of small mobile helium clusters near tung.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UXJARE84\\Hu et al. - 2014 - Dynamics of small mobile helium clusters near tung.pdf:application/pdf}, + number = {SAND2012-7321, 1055634}, + urldate = {2022-02-04}, + author = {San Marchi, Christopher and Somerday, Brian}, + month = sep, + year = {2012}, + doi = {10.2172/1055634}, + pages = {SAND2012--7321, 1055634}, + file = {San Marchi et Somerday - 2012 - Technical reference for hydrogen compatibility of .pdf:D\:\\Logiciels\\data_zotero\\storage\\3KBKK3JA\\San Marchi et Somerday - 2012 - Technical reference for hydrogen compatibility of .pdf:application/pdf}, } -@article{krasheninnikov_helium_2014, - title = {On helium cluster dynamics in tungsten plasma facing components of fusion devices}, - volume = {54}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/54/7/073019}, - doi = {10.1088/0029-5515/54/7/073019}, - abstract = {This paper describes the dynamics of helium clustering behaviour within either a nanometer-sized tendril of fuzz, or a half-space domain, as predicted by a reaction–diffusion model. This analysis has identified a dimensionless parameter, PΔ, which is a balance of the reaction and diffusion actions of insoluble He in a metal matrix and which governs the self-trapping effects of He into growing bubbles within a tendril. The impact of He self-trapping, as well as trapping caused by pre-existing traps in the form of lattice defects or clusters of impurities, within a half-space domain results in the formation of a densely packed layer of nanometer-sized bubbles with high number density. This prediction is consistent with available experimental observations in which a dense zone of helium bubbles is observed in tungsten, which are compared to estimates of the layer characteristics. Direct numerical simulation of the reaction–diffusion cluster dynamics supports the analysis presented here.}, +@techreport{pattrick_calderoni_hydrogen_2010, + title = {Hydrogen {Permeability} of {Incoloy} {800H}, {Inconel} 617, and {Haynes} 230 {Alloys}}, + url = {http://www.osti.gov/servlets/purl/989876-0Fo4wi/}, language = {en}, - number = {7}, - urldate = {2019-10-28}, - journal = {Nuclear Fusion}, - author = {Krasheninnikov, S. I. and Faney, T. and Wirth, B. D.}, - month = may, - year = {2014}, - keywords = {Cluster dynamics}, - pages = {073019}, - file = {Krasheninnikov et al. - 2014 - On helium cluster dynamics in tungsten plasma faci.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L9Y8JQR5\\Krasheninnikov et al. - 2014 - On helium cluster dynamics in tungsten plasma faci.pdf:application/pdf}, + number = {INL/EXT-10-19387, 989876}, + urldate = {2022-02-04}, + author = {{Pattrick Calderoni}}, + month = jul, + year = {2010}, + doi = {10.2172/989876}, + pages = {INL/EXT--10--19387, 989876}, + file = {Pattrick Calderoni - 2010 - Hydrogen Permeability of Incoloy 800H, Inconel 617.pdf:D\:\\Logiciels\\data_zotero\\storage\\VL32ZYBF\\Pattrick Calderoni - 2010 - Hydrogen Permeability of Incoloy 800H, Inconel 617.pdf:application/pdf}, } -@article{de_backer_modeling_2015, - series = {Proceedings of the 12th {International} {Conference} on {Computer} {Simulation} of {Radiation} {Effects} in {Solids}, {Alacant}, {Spain}, 8-13 {June}, 2014}, - title = {Modeling of helium bubble nucleation and growth in austenitic stainless steels using an {Object} {Kinetic} {Monte} {Carlo} method}, - volume = {352}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X14010118}, - doi = {10.1016/j.nimb.2014.11.110}, - abstract = {Implantation of 10keV helium in 316L steel thin foils was performed in JANNuS-Orsay facility and modeled using a multiscale approach. Density Functional Theory (DFT) atomistic calculations [1] were used to obtain the properties of He and He-vacancy clusters, and the Binary Collision Approximation based code MARLOWE was applied to determine the damage and He-ion depth profiles as in [2], [3]. The processes involved in the homogeneous He bubble nucleation and growth were defined and implemented in the Object Kinetic Monte Carlo code LAKIMOCA [4]. In particular as the He to dpa ratio was high, self-trapping of He clusters and the trap mutation of He-vacancy clusters had to be taken into account. With this multiscale approach, the formation of bubbles was modeled up to nanometer-scale size, where bubbles can be observed by Transmission Electron Microscopy. Their densities and sizes were studied as functions of fluence (up to 5×1019He/m2) at two temperatures (473 and 723K) and for different sample thicknesses (25–250nm). It appears that the damage is not only due to the collision cascades but is also strongly controlled by the He accumulation in pressurized bubbles. Comparison with experimental data is discussed and sensible agreement is achieved.}, +@article{chen_diffusion_2017, + title = {Diffusion {Behaviors} of {Hydrogen} {Isotopes} in {Incoloy} {800H}: {A} {First}-{Principles} {Study}}, + volume = {2017}, + issn = {1687-6075, 1687-6083}, + shorttitle = {Diffusion {Behaviors} of {Hydrogen} {Isotopes} in {Incoloy} {800H}}, + url = {https://www.hindawi.com/journals/stni/2017/4038021/}, + doi = {10.1155/2017/4038021}, + abstract = {Incoloy 800H is one of the main stainless steel materials used in steam generators with High Temperature Reactor Pebble-bed Modules (HTR-PM). In this study, the diffusion behaviors of hydrogen isotopes in Incoloy 800H were investigated with first-principle calculations. Numerical results reveal that the starting and ending positions of the diffusion process are the two adjacent and most stable octahedral sites surrounded by Fe atoms and Ni atoms, and the diffusion follows an indirect path via the metastable tetrahedral sites and octahedral sites surrounded by Fe atoms and Cr atoms. The diffusion activation energies of hydrogen (H), deuterium (D), and tritium (T) in Incoloy 800H are investigated by first-principles calculations with the same approximate value of + + Q + = + 0.757 + +  eV; the diffusion coefficient frequency factors are also obtained with values of + + + + D + + + 0 + + + = + 1.56 + × + + + 10 + + + - + 6 + + + + , + + 1.10 + × + + + 10 + + + - + 6 + + + + , and + + 8.99 + × + + + 10 + + + - + 7 + + + +  (m + 2 + /s) for H, D, and T, respectively. Furthermore, the theoretical results are compared with the experimental data, and it is found that both are in agreement with each other. These results are very helpful for understanding the diffusion behaviors of hydrogen isotopes in Incoloy 800H and can be used to guide the tritium source term analysis of secondary circuits in HTR-PM, which are first studied from a microperspective.}, language = {en}, - urldate = {2019-10-28}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {De Backer, A. and Adjanor, G. and Domain, C. and Lescoat, M. L. and Jublot-Leclerc, S. and Fortuna, F. and Gentils, A. and Ortiz, C. J. and Souidi, A. and Becquart, C. S.}, - month = jun, - year = {2015}, - keywords = {Bubble, Monte Carlo}, - pages = {107--114}, - file = {De Backer et al. - 2015 - Modeling of helium bubble nucleation and growth in.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JKKUQFGT\\De Backer et al. - 2015 - Modeling of helium bubble nucleation and growth in.pdf:application/pdf}, + urldate = {2022-02-04}, + journal = {Science and Technology of Nuclear Installations}, + author = {Chen, Hongyu and Li, Hong and Li, Chuan and Cao, Jianzhu and Fang, Chao}, + year = {2017}, + pages = {1--6}, + file = {Chen et al. - 2017 - Diffusion Behaviors of Hydrogen Isotopes in Incolo.pdf:D\:\\Logiciels\\data_zotero\\storage\\XJEXIDKM\\Chen et al. - 2017 - Diffusion Behaviors of Hydrogen Isotopes in Incolo.pdf:application/pdf}, } -@article{kohnert_grouping_2016, - title = {Grouping techniques for large-scale cluster dynamics simulations of reaction diffusion processes}, - volume = {25}, - issn = {0965-0393}, - url = {https://iopscience.iop.org/article/10.1088/1361-651X/25/1/015008}, - doi = {10.1088/1361-651X/25/1/015008}, - abstract = {Cluster dynamics is a powerful, high fidelity, mesoscale method for modeling the kinetic evolution of point defects, impurities, and their clusters in materials and is commonly used in studying radiation damage. These methods excel at modeling nucleation, but often require too many equations to successfully model the long term growth and coarsening that govern microstructural evolution. One solution to this problem is to group equations into a coarser approximation of the cluster size distribution function which can reduce the cost of solution by many orders of magnitude. While such grouping methods have been advanced for a limited class of problems, no reliable method currently exists for the general case. This paper advances a framework for grouping arbitrary cluster dynamics problems, and develops several competing schemes based on that framework. These schemes are each evaluated against a variety of test problems designed to assess their accuracy, robustness, and efficiency.}, +@incollection{causey_416_2012, + address = {Oxford}, + title = {4.16 - {Tritium} {Barriers} and {Tritium} {Diffusion} in {Fusion} {Reactors}}, + isbn = {978-0-08-056033-5}, + url = {https://www.sciencedirect.com/science/article/pii/B9780080560335001166}, + abstract = {Tritium is a radioactive form of hydrogen. Because it is radioactive, its release to the environment must be minimized. Most of the materials used in fusion reactors are metals that have a relatively high permeability for tritium. The fusion community has been working on barrier materials to minimize tritium release by permeation through structural materials. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments. This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The parameters necessary for tritium release calculations for various regions of a fusion reactor are given.}, language = {en}, - number = {1}, - urldate = {2019-10-25}, - journal = {Modelling and Simulation in Materials Science and Engineering}, - author = {Kohnert, Aaron A. and Wirth, Brian D.}, - month = dec, - year = {2016}, - keywords = {Cluster dynamics}, - pages = {015008}, - file = {Kohnert et Wirth - 2016 - Grouping techniques for large-scale cluster dynami.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QE6P64RJ\\Kohnert et Wirth - 2016 - Grouping techniques for large-scale cluster dynami.pdf:application/pdf}, + urldate = {2022-02-04}, + booktitle = {Comprehensive {Nuclear} {Materials}}, + publisher = {Elsevier}, + author = {Causey, R. A. and Karnesky, R. A. and San Marchi, C.}, + editor = {Konings, Rudy J. M.}, + month = jan, + year = {2012}, + doi = {10.1016/B978-0-08-056033-5.00116-6}, + keywords = {Hydrogen, Barriers, Carbides, Deuterium, Diffusion, First wall materials, Fusion, Metals, Nitrides, Oxides, Permeation, Recombination, Solubility, Structural materials, Tritium}, + pages = {511--549}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\QFUEQZ2R\\Causey et al. - 2012 - 4.16 - Tritium Barriers and Tritium Diffusion in F.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\Z3AYIJMQ\\B9780080560335001166.html:text/html}, } -@article{perez_mobility_2017, - title = {The mobility of small vacancy/helium complexes in tungsten and its impact on retention in fusion-relevant conditions}, - volume = {7}, - issn = {2045-2322}, - doi = {10.1038/s41598-017-02428-2}, - abstract = {Tungsten is a promising plasma facing material for fusion reactors. Despite many favorable properties, helium ions incoming from the plasma are known to dramatically affect the microstructure of tungsten, leading to bubble growth, blistering, and/or to the formation of fuzz. In order to develop mitigation strategies, it is essential to understand the atomistic processes that lead to bubble formation and subsequent microstructural changes. In this work, we use large-scale Accelerated Molecular Dynamics simulations to investigate small (N = 1,2) V N He M vacancy/helium complexes, which serve as the nuclei for larger helium bubble growth, over timescales reaching into the milliseconds under conditions typical of the operation of fusion reactors. These complexes can interconvert between different I L V N+L He M variants via Frenkel pair nucleation (leading to the creation of a additional vacancy/interstitial pair) and annihilation events; sequences of these events can lead to net migration of these embryonic bubbles. The competition between nucleation and annihilation produces a very complex dependence of the diffusivity on the number of heliums. Finally, through cluster dynamics simulations, we show that diffusion of these complexes provides an efficient pathway for helium release at fluxes expected in fusion reactors, and hence that accounting for the mobility of these complexes is crucial.}, - language = {eng}, - number = {1}, - journal = {Scientific Reports}, - author = {Perez, Danny and Sandoval, Luis and Blondel, Sophie and Wirth, Brian D. and Uberuaga, Blas P. and Voter, Arthur F.}, - year = {2017}, - pmid = {28559588}, - pmcid = {PMC5449393}, - keywords = {Molecular Dynamics}, - pages = {2522}, - file = {Perez et al. - 2017 - The mobility of small vacancyhelium complexes in .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2TPUXBS5\\Perez et al. - 2017 - The mobility of small vacancyhelium complexes in .pdf:application/pdf}, +@article{hurley_role_2016, + title = {Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600: {Study} coupling thermal desorption mass spectroscopy with numerical simulation}, + volume = {41}, + issn = {0360-3199}, + shorttitle = {Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600}, + url = {https://www.sciencedirect.com/science/article/pii/S0360319916300702}, + doi = {10.1016/j.ijhydene.2016.07.038}, + abstract = {The role grain boundaries play in the diffusion of hydrogen in polycrystalline alloys has long been debated. Some researchers have found that grain boundaries have an accelerating effect on the transport of hydrogen across a metal membrane, while others have stated this network of sites may slow the diffusion of hydrogen or have a mixed effect depending on grain size and orientation. Thermal desorption mass spectroscopy (TDS) was used to study the diffusion of deuterium, from 294 K to 550 K, in model single crystal and polycrystalline nickel base alloy, alloy 600, having a grain size of several tens of micrometers. Using a numerical routine, solving Fick's second law of diffusion, TDS spectra were fit or simulated. The derived diffusion constant parameters (D0 = (1.0 ± 0.5)·10−2 cm2 s−1 and ED = (45 ± 4) kJ mol−1) for the polycrystalline alloy adequately predict and simulate the deuterium desorption from the single crystal during TDS testing. Furthermore, in the temperature range and for the grain size studied no significant effect of grain boundaries on the diffusion of deuterium in alloy 600 was observed. Consequently, the measured diffusion parameters are representative of interstitial diffusion in the alloy.}, + language = {en}, + number = {38}, + urldate = {2022-02-04}, + journal = {International Journal of Hydrogen Energy}, + author = {Hurley, Caitlin and Martin, Frantz and Marchetti, Loïc and Chêne, Jacques and Blanc, Christine and Andrieu, Eric}, + month = oct, + year = {2016}, + keywords = {Hydrogen, Deuterium, Diffusion, Grain boundaries, Ni base alloy, Thermal desorption mass spectroscopy}, + pages = {17145--17153}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5JERLF6X\\Hurley et al. - 2016 - Role of grain boundaries in the diffusion of hydro.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\IWN8IM8S\\S0360319916300702.html:text/html}, } -@article{yang_kinetic_2017, - title = {Kinetic {Monte} {Carlo} {Simulations} of {Helium} {Cluster} {Nucleation} in {Tungsten} with {Preexisting} {Vacancies}}, - volume = {71}, +@article{zhang_diffusion_2020, + title = {Diffusion {Characterization} of {Hydrogen} {Isotopes} in {Hastelloy} {N} {Alloy} for the {Application} of {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} ({FHRs})}, + volume = {76}, issn = {1536-1055}, - url = {https://doi.org/10.13182/FST16-111}, - doi = {10.13182/FST16-111}, - abstract = {The object kinetic Monte Carlo code Kinetic Simulations Of Microstructure Evolution (KSOME) was used to study the subsurface helium clustering behavior in tungsten as a function of temperature, helium implantation rate, and vacancy concentration. The simulations evaluated helium implantation fluxes from 1022 to 1026 m−2 · s−1 at temperatures from 473 to 1473 K for 100-eV helium ions implanted below tungsten surfaces and for vacancy concentrations between 1 and 50 parts per million. Such vacancy concentrations far exceed thermodynamic equilibrium values but are consistent with supersaturated concentrations expected during concurrent, or preexisting, neutron irradiation. The thermodynamics and kinetic parameters to describe helium diffusion and clustering are input to KSOME based on values obtained from atomistic simulation results. These kinetic Monte Carlo results clearly delineate two different regimes of helium cluster nucleation, one dominated by helium self-trapping at high implantation rates and lower temperatures and one where helium–vacancy trapping dominates the helium cluster nucleation at lower implantation rates and higher temperatures. The transition between these regimes has been mapped as a function of implantation rate, temperature, and vacancy concentration and can provide guidance to understand the conditions under which neutron irradiation effects may contribute to subsurface gas nucleation in tungsten plasma-facing components.}, - number = {1}, - urldate = {2019-10-07}, + url = {https://doi.org/10.1080/15361055.2020.1725368}, + doi = {10.1080/15361055.2020.1725368}, + abstract = {With the method of gas-driven permeation, a series of permeation experiments was carried out using Hastelloy N alloy membrane in an elevated temperature range of 400°C to 800°C with different hydrogen isotopes. A complete set of permeability, diffusivity, and Sieverts’ constant for hydrogen and deuterium in Hastelloy N alloy was successfully obtained. The isotope effect in the diffusion process was analyzed and compared with references. The ratios of diffusive transport parameters for hydrogen and deuterium were a permeability ratio of ФH/ФD = 1.32exp(0.34kJ/RT), a diffusivity ratio of DH/DD = 1.15exp(−0.41kJ/RT), and a Sieverts’ constant ratio of KS,H/KS,D = 1.16exp(0.21kJ/RT). The result that the permeation flux of deuterium was decreased after introducing hydrogen could be used to suppress the permeation of tritium in future tritium control of the Fluoride-salt-cooled High-temperature Reactor (FHR). Compared with NiO, the Cr2O3 formed in the surface oxidation layer of Hastelloy N alloy showed better hydrogen permeation barrier performance after baking above 700°C in air.}, + number = {4}, + urldate = {2022-02-04}, journal = {Fusion Science and Technology}, - author = {Yang, Zhangcan and Blondel, Sophie and Hammond, Karl D. and Wirth, Brian D.}, + author = {Zhang, Dongxun and Liu, Wei and Liu, Wenguan}, + month = may, + year = {2020}, + note = {Publisher: Taylor \& Francis +\_eprint: https://doi.org/10.1080/15361055.2020.1725368}, + keywords = {fluoride salt, Hastelloy N alloy, permeation, surface oxidation}, + pages = {543--552}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\L47DVY64\\Zhang et al. - 2020 - Diffusion Characterization of Hydrogen Isotopes in.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\M5GTWE8E\\15361055.2020.html:text/html}, +} + +@article{diaz-rodriguez_direct_2022, + title = {Direct observation of hydrogen permeation through grain boundaries in tungsten}, + issn = {2522-574X}, + url = {https://doi.org/10.1007/s42247-021-00344-w}, + doi = {10.1007/s42247-021-00344-w}, + abstract = {In this paper, we report on an enhanced hydrogen permeation effect along grain boundaries in tungsten. Sputtered nanocolumnar tungsten layers (column lateral dimensions 100–150 nm and layer thickness 2 μm) were analysed by hydrogen permeation measurements in the temperature range 520–705 K. The experiments constitute a direct observation of this effect, previously postulated by means of a combination of indirect experiments and simulations and considered controversial due to the lack of direct measurements. DFT results support this observation since (i) the hydrogen binding energy to the grain boundary is 1.05 eV and (ii) the migration energies along the grain boundary and along the bulk are 0.12 eV and 0.20 eV, respectively. OKMC simulations, parametrized by DFT data, were used as a supporting tool to attain a better understanding of the involved phenomena. The OKMC results are also compatible with the observations. Indeed, they show that the fraction of hydrogen flux along grain boundaries in the steady-state permeation regime increases when decreasing the ratio of lateral dimensions to length of the nanocolumns, rapidly approaching unity when this ratio is {\textless} 2. Therefore, grain boundaries act as preferential migration pathways for H atoms at the studied temperature range in the studied samples. This behaviour has interesting implications to reduce the retention of hydrogen in several applications, in particular, fusion materials exposed to plasma discharges.}, + language = {en}, + urldate = {2022-01-31}, + journal = {Emergent Materials}, + author = {Díaz-Rodríguez, Pablo and Panizo-Laiz, Miguel and González, César and Iglesias, Roberto and Martín-Bragado, Ignacio and González-Arrabal, Raquel and Perlado, Jose Manuel and Peña-Rodríguez, Ovidio and Rivera, Antonio}, month = jan, - year = {2017}, - keywords = {Monte Carlo}, - pages = {60--74}, + year = {2022}, + annote = {permeation experiments on Nanostructured tungsten +  +Shows higher permeability than in litterature +suggests grain boundary accelerated diffusion +  +--{\textgreater} towards an inostropic material?}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\6JCI44VX\\Díaz-Rodríguez et al. - 2022 - Direct observation of hydrogen permeation through .pdf:application/pdf}, } -@article{blondel_continuum-scale_2018, - title = {Continuum-scale modeling of helium bubble bursting under plasma-exposed tungsten surfaces}, - volume = {58}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/aae8ef}, - doi = {10.1088/1741-4326/aae8ef}, - abstract = {We present a comparison between a continuum-scale drift-diffusion-reaction cluster dynamics prediction of helium retention in low-energy helium plasma exposed tungsten and experimental measurements, in a temperature regime that did not produce tungsten fuzz. Our cluster dynamics model, Xolotl, has been successfully benchmarked to high helium implantation flux MD simulations at relatively low implanted fluence. In this article, we also describe the extension of the Xolotl DDR model to incorporate the effect of bubble bursting, which is observed in very high rate MD simulations, as well as MD simulations at longer times than simulated in our prior benchmarking comparison. The bursting model parameters have been tuned by comparing to MD simulations at a flux of 5.0 × 1027 m−2 s−1, and also compared to lower implanted fluence simulations performed at 4.0 × 1025 m−2 s−1. This article then reports on the consistency of the Xolotl predictions with respect to the size of the simulated cluster phase space (i.e. the maximum cluster size), initial vacancy concentration, and bubble growth trajectory (maximum number of helium atoms per vacancy). Finally, our simulation results are compared to helium plasma experiments that did not produce fuzz. While the Xolotl predictions including bubble bursting are in quantitative agreement with high-flux MD simulations, the initial comparison to plasma exposure experiments at a flux on the order of 1021 m−2 s−1 disagree by more than an order of magnitude, and in fact cannot reproduce the trends in helium retention with varying exposure temperature. Modifying the initial vacancy concentrations and helium cluster diffusion behavior in Xolotl leads to a reasonable agreement with the experimental observations, although the underlying physical explanation for these modifications remains unclear. The predicted helium content at experimentally relevant fluxes has been shown to be relatively insensitive to the parameters used in the bubble bursting model implemented in Xolotl, although these parameters have a larger influence at higher flux. More systematic comparisons between the modeling predictions with both experiments and MD simulation results is expected to improve the bubble bursting model in Xolotl in the future.}, +@article{van_den_kerkhof_impact_2021, + title = {Impact of {ELM} mitigation on the {ITER} monoblock thermal behavior and the tungsten recrystallization depth}, + volume = {27}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121000867}, + doi = {10.1016/j.nme.2021.101009}, + abstract = {Type I Edge Localized Modes (ELMs) occur naturally in H-mode plasmas, the operational regime envisaged for ITER, and lead to high temporal heat load peaks on plasma-facing components that might induce surface melting and deteriorated material properties due to recrystallization. ELM mitigation techniques are being developed that either attempt to fully suppress the ELM, e.g. using resonant magnetic perturbations (RMP), or to trigger the ELM at higher frequencies, intending to reduce its energy content and hence the heat load peak. In this paper, the effect of the increased ELM frequency achieved by ELM mitigation techniques on the ITER tungsten divertor monoblock thermal and recrystallization behavior is numerically analyzed by solving the unsteady heat conduction equation when repeatedly exposing the monoblock to ELM-like heat loads under ITER baseline burning plasma operating conditions. The impinging heat load is based on a set of empirical relations readily found in literature and the recrystallization fraction is computed using an empirical data fit which is based on the non-isothermal JMAK equation as function of temperature and time. Uncertainties such as the statistical spread on empirical relations and the unknown inter-ELM heat load, as well as the effect of the ELM frequency, are quantified by a parameter scan. Adopting the recently developed concept of a ‘recrystallization budget’ to determine the allowed monoblock heat loads [G. De Temmerman et al., PPCF 60 (2018) 0044018], it was found that ELM frequencies between 25 – 50 Hz are allowed for inter-ELM heat loads between 9 – 6 MW m−2 , respectively, when assuming that the scaling for the peak ELM target energy density in [T. Eich et al., NME 12 (2017) 84-90] holds. This provides a new limit for ELM mitigation strategies in ITER.}, language = {en}, - number = {12}, - urldate = {2019-10-07}, - journal = {Nuclear Fusion}, - author = {Blondel, Sophie and Bernholdt, David E. and Hammond, Karl D. and Wirth, Brian D.}, - month = nov, - year = {2018}, - keywords = {Cluster dynamics}, - pages = {126034}, - file = {Blondel et al. - 2018 - Continuum-scale modeling of helium bubble bursting.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KSP2ZTJ8\\Blondel et al. - 2018 - Continuum-scale modeling of helium bubble bursting.pdf:application/pdf}, + urldate = {2022-01-28}, + journal = {Nuclear Materials and Energy}, + author = {Van den Kerkhof, S. and Blommaert, M. and Pitts, R. A. and Dekeyser, W. and Carli, S. and Baelmans, M.}, + month = jun, + year = {2021}, + keywords = {ITER, Edge Localized Modes, ELM mitigation, Heat loads, Tungsten recrystallization}, + pages = {101009}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\RZPFEKXI\\S2352179121000867.html:text/html}, } -@article{hammond_large-scale_2018, - title = {Large-scale atomistic simulations of low-energy helium implantation into tungsten single crystals}, - volume = {144}, - issn = {1359-6454}, - url = {http://www.sciencedirect.com/science/article/pii/S1359645417308315}, - doi = {10.1016/j.actamat.2017.09.061}, - abstract = {Large-scale molecular dynamics simulations of post-implantation helium behavior in plasma-facing tungsten single crystals reveal orientation-dependent depth profiles, surface evolution patterns, and other crystallographic and diffusion-related characteristics of helium behavior in tungsten during the first microsecond. The flux of implanted helium atoms studied, Γ ≈ 4 × 1025 m−2 s−1, is about one order of magnitude larger than that expected in ITER, the experimental fusion reactor currently being constructed in France. With simulation times on the order of 1 μs, these results serve to discover the mechanisms involved in surface evolution as well as to serve as benchmarks for coarse-grained simulations such as kinetic Monte Carlo and continuum-scale drift–reaction–diffusion cluster dynamics simulations. The findings of our large-scale simulations are significant due to diminished finite-size effects and the longer times reached (corresponding to higher fluences). Specifically, our findings are drastically different from findings published previously in the literature for (001) surfaces under a helium flux of Γ ∼ 1028 m−2 s−1, which is typical of smaller size and shorter time atomistic simulations. In particular, this study highlights the atomic-scale materials processes relevant to helium entrapment and transport in metals, which have implications not only for nuclear fusion–relevant processes, but also helium-induced embrittlement in irradiated materials such as hospital equipment and fission reactor materials.}, - urldate = {2019-10-07}, - journal = {Acta Materialia}, - author = {Hammond, Karl D. and Blondel, Sophie and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, - month = feb, - year = {2018}, - keywords = {Molecular Dynamics, Helium, Tungsten, Nuclear fusion, Molecular dynamics, Plasma-facing material}, - pages = {561--578}, - file = {Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6Z7V7EV2\\Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H28LWS3B\\S1359645417308315.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\75S2EHRZ\\Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:application/pdf}, +@techreport{beck_research_1960, + title = {{RESEARCH} {AND} {DEVELOPMENT} {OF} {METAL} {HYDRIDES}. {Summary} {Report} for {October} 1, 1958-{September} 30, 1960}, + url = {https://www.osti.gov/biblio/4790244-research-development-metal-hydrides-summary-report-october-september}, + abstract = {A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding or controlling epithermal reactors. (auth)}, + language = {English}, + number = {LAR-10}, + urldate = {2022-01-26}, + institution = {Denver. Univ. Denver Research Inst.}, + author = {Beck, R. L.}, + month = nov, + year = {1960}, + doi = {10.2172/4790244}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EGU852SR\\Beck - 1960 - RESEARCH AND DEVELOPMENT OF METAL HYDRIDES. Summar.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XHU27Q9R\\4790244-research-development-metal-hydrides-summary-report-october-september.html:text/html}, } -@article{blondel_benchmarks_2017, - title = {Benchmarks and {Tests} of a {Multidimensional} {Cluster} {Dynamics} {Model} of {Helium} {Implantation} in {Tungsten}}, - volume = {71}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST16-109}, - doi = {10.13182/FST16-109}, - abstract = {We present a hierarchical multiscale modeling study of implanted helium (He) segregation near grain boundaries (GBs) of tungsten. We extend our spatially dependent cluster dynamics model to two spatial dimensions in order to take into account the biased drift of mobile He clusters toward the GBs observed in atomic-scale simulations. We are able to reproduce the results from large-scale molecular dynamics simulations near and away from the GBs at low fluence with the extended cluster dynamics model. We suggest and verify that the sink (surface and GB) strengths are attenuated by the increasing concentration of He clusters at high fluence. This cluster dynamics model continues to set the stage for development of fully atomistically informed, coarse-grained models for computationally efficient predictions of He retention and surface morphological evolution, advancing progress toward the goal of efficient and optimal design of plasma-facing components.}, - number = {1}, - urldate = {2019-10-07}, - journal = {Fusion Science and Technology}, - author = {Blondel, Sophie and Bernholdt, David E. and Hammond, Karl D. and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, - month = jan, - year = {2017}, - keywords = {Cluster dynamics}, - pages = {84--92}, +@article{segantin_exploration_2020, + title = {Exploration of power conversion thermodynamic cycles for {ARC} fusion reactor}, + volume = {155}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379620301939}, + doi = {10.1016/j.fusengdes.2020.111645}, + abstract = {In the worldwide energy industry, nuclear fusion could be a breakthrough in the medium-long term. One promising fusion machine under design at Massachusetts Institute of Technology is ARC reactor. It is likely that the first nuclear fusion plants will rely on a traditional thermodynamic cycle for the downstream power energy conversion. In this framework, one of the design aspects is to maximize the thermal efficiency. In the present paper the thermodynamic cycles, which could be adopted in ARC rector, are explored. Three cycles have been considered: the Rankine, the Brayton and a combined cycle. For the gas adopted in the Brayton and combined cycles, two options have been investigated: supercritical Helium and supercritical CO2. A comparison among thermal efficiency and preliminary considerations on component integrity’s, plant feasibility and economics of each studied configurations has been discussed to identify the possible best option for ARC reactor. The results show that a regenerative CO2 Brayton cycle with intercooler and re-heating systems is the most promising one. Such configurations is able to reach a thermodynamic efficiency of up to 0.6.}, + language = {en}, + urldate = {2022-01-26}, + journal = {Fusion Engineering and Design}, + author = {Segantin, Stefano and Bersano, Andrea and Falcone, Nicolò and Testoni, Raffaella}, + month = jun, + year = {2020}, + keywords = {ARC, Balance of plant, Nuclear reactors, Power conversion, Thermodynamic cycles, Thermodynamic efficiency}, + pages = {111645}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\JJWLYNL5\\S0920379620301939.html:text/html}, } -@article{boisse_modelling_2014, - series = {Proceedings of the 16th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-16)}, - title = {Modelling self trapping and trap mutation in tungsten using {DFT} and {Molecular} {Dynamics} with an empirical potential based on {DFT}}, - volume = {455}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514001032}, - doi = {10.1016/j.jnucmat.2014.02.031}, - abstract = {Density Functional Theory calculations and Molecular Dynamics with a recently developed potential for W–He were used to evaluate the thermal stability of helium–vacancy clusters (nHe.mv) as well as pure interstitial helium clusters in tungsten. The stability of such objects results from a competitive process between thermal emission of vacancies, self interstitial atoms (SIAs) and helium, depending on the helium-to-vacancy ratio in mixed clusters or helium number in pure interstitial helium clusters. We investigated in particular the thermodynamics and kinetics of self trapping and trap mutation, i.e. the emission of one SIA along with the creation of one vacancy from a vacancy–helium or pure helium object.}, - language = {en}, - number = {1}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Boisse, J. and Domain, C. and Becquart, C. S.}, - month = dec, - year = {2014}, - keywords = {Density Functional Theory, Molecular Dynamics}, - pages = {10--15}, - file = {Boisse et al. - 2014 - Modelling self trapping and trap mutation in tungs.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9D6A77RY\\Boisse et al. - 2014 - Modelling self trapping and trap mutation in tungs.pdf:application/pdf}, +@phdthesis{mangiarotti_design_2016, + type = {Thesis}, + title = {Design of demountable toroidal field coils with {REBCO} superconductors for a fusion reactor}, + copyright = {M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.}, + url = {https://dspace.mit.edu/handle/1721.1/103659}, + abstract = {The recent development of REBCO superconducting tapes, cabling methods and joint concepts could be a revolutionary development for magnetic fusion. REBCO has significantly better performance at high magnetic fields than traditional low temperature superconductors (LTS), and can be operated at a higher temperature than LTS for reduced thermodynamic cost of cooling. Use of REBCO superconductors in the magnet systems of tokamaks allows building demountable toroidal field (TF) coils, greatly simplifying reactor construction and maintenance. A demountable TF coil system with REBCO superconductors for a fusion reactor has been conceptually designed. The coil system operates at 20 K, with a maximum magnetic field of 20 T. The magnets are divided into two coil segments and can be detached and remounted to allow the internal components of the reactor to be removed vertically as one piece. Operating at 20 T and 20 K, the stress in most of the coils is acceptable (less than 2/3 the yield strength and less than 1/2 the ultimate tensile strength of the structural materials). The strain in the superconductors is lower than the reversible degradation limit. The electrical resistance in each conductor joint is 10 n [Omega]. The total heat generation in the reactor superconducting TF magnets is approximately 1.9 MW, of which about 25 \% is nuclear heating and 75 \% joint heating. 71 MW of electricity are required for cooling the coils at 20 K, about 7 \% of the electric energy the reactor generates. The expected time to warm-up the magnets from the operation temperature to room temperature is 7 days, and approximately the same for cool-down back to the operation temperature. The analysis of the conceptual magnet design is encouraging, as no insuperable problems have been identified. This conceptual design can be used as a starting point for a full engineering design of demountable fusion reactors magnets.}, + language = {eng}, + urldate = {2022-01-26}, + school = {Massachusetts Institute of Technology}, + author = {Mangiarotti, Franco Julio}, + year = {2016}, + note = {Accepted: 2016-07-18T19:10:37Z}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\BIUNBG5Q\\Mangiarotti - 2016 - Design of demountable toroidal field coils with RE.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TWISVT2V\\103659.html:text/html}, } -@article{lasa_md_2013, - series = {Proceedings of the 11th {Computer} {Simulation} of {Radiation} {Effects} in {Solids} ({COSIRES}) {Conference} {Santa} {Fe}, {New} {Mexico}, {USA}, {July} 24-29, 2012}, - title = {{MD} simulations of onset of tungsten fuzz formation under helium irradiation}, - volume = {303}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X12007719}, - doi = {10.1016/j.nimb.2012.11.029}, - abstract = {When helium (He) escapes a fusion reactor plasma, a tungsten (W)-based divertor may, under some conditions, form a fuzz-like nano-morphology. This is a highly undesired phenomenon for the divertor, and is not well understood. We performed molecular dynamics simulations of high fluence He and also C-seeded He (He+C) irradiation on W, focusing on the effect of the high fluence, the temperature and the impurities on the onset of the structure formation. We concluded that MD reproduces the experimentally found square root of time dependence of the surface growth. The He atomic density decreases when increasing the number of He atoms in the cell. A higher temperature causes a larger bubble growth and desorption activity, specially for the pure He irradiation cases. It also it leads to W recrystallization for the He+C irradiation cases. Carbon acts as a local He trap for small clusters or single atoms and causes a larger loss of crystallinity of the W surface.}, +@article{creely_overview_2020, + title = {Overview of the {SPARC} tokamak}, + volume = {86}, + issn = {0022-3778, 1469-7807}, + url = {https://www.cambridge.org/core/journals/journal-of-plasma-physics/article/overview-of-the-sparc-tokamak/DD3C44ECD26F5EACC554811764EF9FF0}, + doi = {10.1017/S0022377820001257}, + abstract = {The SPARC tokamak is a critical next step towards commercial fusion energy. SPARC is designed as a high-field (B0=12.2B0=12.2B\_0 = 12.2 T), compact (R0=1.85R0=1.85R\_0 = 1.85 m, a=0.57a=0.57a = 0.57 m), superconducting, D-T tokamak with the goal of producing fusion gain Q{\textgreater}2Q{\textgreater}2Q{\textgreater}2 from a magnetically confined fusion plasma for the first time. Currently under design, SPARC will continue the high-field path of the Alcator series of tokamaks, utilizing new magnets based on rare earth barium copper oxide high-temperature superconductors to achieve high performance in a compact device. The goal of Q{\textgreater}2Q{\textgreater}2Q{\textgreater}2 is achievable with conservative physics assumptions (H98,y2=0.7H98,y2=0.7H\_\{98,y2\} = 0.7) and, with the nominal assumption of H98,y2=1H98,y2=1H\_\{98,y2\} = 1, SPARC is projected to attain Q≈11Q≈11Q {\textbackslash}approx 11 and Pfusion≈140Pfusion≈140P\_\{{\textbackslash}textrm \{fusion\}\} {\textbackslash}approx 140 MW. SPARC will therefore constitute a unique platform for burning plasma physics research with high density (⟨ne⟩≈3×1020 m−3⟨ne⟩≈3×1020 m−3{\textbackslash}langle n\_\{e\} {\textbackslash}rangle {\textbackslash}approx 3 {\textbackslash}times 10{\textasciicircum}\{20\}{\textbackslash} {\textbackslash}textrm \{m\}{\textasciicircum}\{-3\}), high temperature (⟨Te⟩≈7⟨Te⟩≈7{\textbackslash}langle T\_e {\textbackslash}rangle {\textbackslash}approx 7 keV) and high power density (Pfusion/Vplasma≈7 MWm−3Pfusion/Vplasma≈7 MWm−3P\_\{{\textbackslash}textrm \{fusion\}\}/V\_\{{\textbackslash}textrm \{plasma\}\} {\textbackslash}approx 7{\textbackslash} {\textbackslash}textrm \{MW\}{\textbackslash},{\textbackslash}textrm \{m\}{\textasciicircum}\{-3\}) relevant to fusion power plants. SPARC's place in the path to commercial fusion energy, its parameters and the current status of SPARC design work are presented. This work also describes the basis for global performance projections and summarizes some of the physics analysis that is presented in greater detail in the companion articles of this collection.}, language = {en}, - urldate = {2019-10-30}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Lasa, A. and Henriksson, K. O. E. and Nordlund, K.}, - month = may, - year = {2013}, - keywords = {Bubble, Molecular Dynamics}, - pages = {156--161}, - file = {Lasa et al. - 2013 - MD simulations of onset of tungsten fuzz formation.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GVK3G6XA\\Lasa et al. - 2013 - MD simulations of onset of tungsten fuzz formation.pdf:application/pdf}, + number = {5}, + urldate = {2022-01-26}, + journal = {Journal of Plasma Physics}, + author = {Creely, A. J. and Greenwald, M. J. and Ballinger, S. B. and Brunner, D. and Canik, J. and Doody, J. and Fülöp, T. and Garnier, D. T. and Granetz, R. and Gray, T. K. and Holland, C. and Howard, N. T. and Hughes, J. W. and Irby, J. H. and Izzo, V. A. and Kramer, G. J. and Kuang, A. Q. and LaBombard, B. and Lin, Y. and Lipschultz, B. and Logan, N. C. and Lore, J. D. and Marmar, E. S. and Montes, K. and Mumgaard, R. T. and Paz-Soldan, C. and Rea, C. and Reinke, M. L. and Rodriguez-Fernandez, P. and Särkimäki, K. and Sciortino, F. and Scott, S. D. and Snicker, A. and Snyder, P. B. and Sorbom, B. N. and Sweeney, R. and Tinguely, R. A. and Tolman, E. A. and Umansky, M. and Vallhagen, O. and Varje, J. and Whyte, D. G. and Wright, J. C. and Wukitch, S. J. and Zhu, J. and Team, the SPARC}, + month = oct, + year = {2020}, + note = {Publisher: Cambridge University Press}, + keywords = {fusion plasma, plasma confinement, plasma devices}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\WPBNM33F\\Creely et al. - 2020 - Overview of the SPARC tokamak.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\A9A42L5X\\DD3C44ECD26F5EACC554811764EF9FF0.html:text/html}, } -@article{sandoval_overview_2019, - title = {An {Overview} of {Recent} {Standard} and {Accelerated} {Molecular} {Dynamics} {Simulations} of {Helium} {Behavior} in {Tungsten}}, - volume = {12}, - issn = {1996-1944}, - url = {https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6721179/}, - doi = {10.3390/ma12162500}, - abstract = {One of the most critical challenges for the successful adoption of nuclear fusion power corresponds to plasma-facing materials. Due to its favorable properties in this context (low sputtering yield, high thermal conductivity, high melting point, among others), tungsten is a leading candidate material. Nevertheless, tungsten is affected by the plasma and fusion byproducts. Irradiation by helium nuclei, in particular, strongly modifies the surface structure by a synergy of processes, whose origin is the nucleation and growth of helium bubbles. In this review, we present recent advances in the understanding of helium effects in tungsten from a simulational approach based on accelerated molecular dynamics, which emphasizes the use of realistic parameters, as are expected in experimental and operational fusion power conditions.}, - number = {16}, - urldate = {2019-10-28}, - journal = {Materials}, - author = {Sandoval, Luis and Perez, Danny and Uberuaga, Blas P. and Voter, Arthur F.}, - month = aug, - year = {2019}, - pmid = {31394714}, - pmcid = {PMC6721179}, - keywords = {Molecular Dynamics}, - file = {Sandoval et al. - 2019 - An Overview of Recent Standard and Accelerated Mol.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9M2CDM2D\\Sandoval et al. - 2019 - An Overview of Recent Standard and Accelerated Mol.pdf:application/pdf}, +@article{zeng_development_2018, + title = {Development of the {Tritium} {Transport} {Analysis} {Code} for the {Thorium}-{Based} {Molten} {Salt} {Reactor}}, + volume = {203}, + issn = {0029-5450}, + url = {https://doi.org/10.1080/00295450.2018.1433408}, + doi = {10.1080/00295450.2018.1433408}, + abstract = {The Thorium-Based Molten Salt Reactor (TMSR) has been highlighted for its safety, economy, and nuclear nonproliferation. A program for developing the TMSR system has been launched in Shanghai Institute of Applied Physics, Chinese Academy of Sciences. In the TMSR system, mixtures of LiF and BeF2, termed FLiBe, are proposed and used as the primary coolant salt, in which tritium is produced mainly by the neutron reactions of lithium. In the TMSR system, at high temperatures, tritium can permeate through metal walls to the surroundings, leading to a potential radiological hazard. Thus, tritium control becomes a major problem hindering the development of the TMSR system. Evaluation of the tritium distribution is necessary for tritium control in the TMSR system. In this study, the Tritium Transport Analysis Code (TTAC) has been developed for simulating the tritium behaviors in the TMSR system (hence, the code TMSR-TTAC), such as tritium chemical forms in coolant salts, tritium transport behaviors, and tritium distribution in the system. The model code is developed by the MATLAB/SIMULINK package, and it is based on the mass balance equations of the tritium-containing species and hydrogen. TMSR-TTAC is benchmarked with the molten salt reactor model, which is based on Molten Salt Reactor Experiment designs. The results show that TMSR-TTAC has the ability to calculate the tritium distribution in the TMSR system.}, + number = {1}, + urldate = {2022-01-24}, + journal = {Nuclear Technology}, + author = {Zeng, Youshi and Wu, Shengwei and Liu, Wei and Wang, Guanghua and Qian, Nan and Wu, Xiaoling and Liu, Wenguan and Huang, Yu and Qian, Yuan}, + month = jul, + year = {2018}, + note = {Publisher: Taylor \& Francis +\_eprint: https://doi.org/10.1080/00295450.2018.1433408}, + keywords = {Thorium-based molten salt reactor, tritium distribution, tritium transport}, + pages = {48--57}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DMS6YA55\\Zeng et al. - 2018 - Development of the Tritium Transport Analysis Code.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\T5RKNWYJ\\00295450.2018.html:text/html}, } -@article{hammond_helium_2019, - title = {Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations}, - volume = {59}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab12f6}, - doi = {10.1088/1741-4326/ab12f6}, - abstract = {We investigate helium flux effects on helium transport and surface evolution in plasma-facing tungsten using molecular dynamics. The simulations span two orders of magnitude, from ITER-relevant levels to those more typical of simulations published to date. Simulation times of up to 2.5 µs (corresponding to actual fluences of m−2) are achieved, revealing concerted bubble-bursting events that are responsible for significant and very sudden changes in surface morphology. The depth distribution of helium depends very strongly on helium flux: helium self-trapping becomes more probable near the surface at high flux, and a layer of near-surface bubbles forms. Helium retention prior to the onset of bubble bursting is also substantially lower at low flux than it is at high flux. Surface features at low fluence are correlated with the positions of bubbles, but at high fluence, bubbles tend to coalesce, venting to the surface at one or more locations and leaving large interconnected cavities below the surface. Ruptured bubbles may serve as pathways deeper into the material, allowing helium to bypass the layer of near-surface bubbles and fill deeper, potentially much larger, bubbles that can produce more substantial surface features. Deeper bubbles also emit prismatic dislocation loops that can fill in cavities closer to the surface. Our results suggest that nearly all molecular dynamics simulations published to date are hampered by finite-size effects, and that helium flux is a very important parameter in determining the behavior of helium in plasma-facing components.}, +@article{nakamura_hydrogen_2015, + title = {Hydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket}, + abstract = {Mixed fluoride molten salts Flinak (LiF+NaF+KF) and Flibe (LiF+BeF2) are expected to work as a tritium breeder in a fusion reactor blanket along with coolant and uranium fuel dissolver in a molten salt fission reactor. In this study, after making the molten salts in an electric furnace and purifying the salts by HF, experiments were performed to determine the behavior of H2 permeation through the fluoride molten salts at static conditions in the range of 500-600 °C using an apparatus composed of tertiary cylindrical Monel400 tubes. In addition, transient H2 diffusion equations in molten salts were solved, and results were compared with experimental effluent H2 concentration curves. It is proved experimentally that the H2 permeability through Flibe or Flinak has linear pressure dependence, and permeability, diffusivity and solubility of H2 in the fluoride molten salts are correlated to their respective Arrhenius-type equations.}, language = {en}, - number = {6}, - urldate = {2019-10-25}, - journal = {Nuclear Fusion}, - author = {Hammond, Karl D. and Naeger, Ian V. and Widanagamaachchi, Wathsala and Lo, Li-Ta and Maroudas, Dimitrios and Wirth, Brian D.}, - month = may, - year = {2019}, - keywords = {Molecular Dynamics}, - pages = {066035}, - file = {Hammond et al. - 2019 - Helium flux effects on bubble growth and surface m.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QZAGN88L\\Hammond et al. - 2019 - Helium flux effects on bubble growth and surface m.pdf:application/pdf}, + author = {Nakamura, Akira and Fukada, Satoshi and Nishiumi, Ryosuke}, + year = {2015}, + pages = {5}, + file = {Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:D\:\\Logiciels\\data_zotero\\storage\\RN3G2BNI\\Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:application/pdf;Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:D\:\\Logiciels\\data_zotero\\storage\\BKLAAYU5\\Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:application/pdf}, } -@article{jourdan_variable-gap_2011, - title = {A variable-gap model for calculating free energies of helium bubbles in metals}, - volume = {418}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311511006921}, - doi = {10.1016/j.jnucmat.2011.07.019}, - abstract = {We propose a variable-gap energy model for helium bubbles in metals, based on molecular dynamics (MD) calculations. The emphasis is put on the appropriate description of the helium-metal repulsion, which can be modelled as a variable-size gap between regions occupied by helium and metal atoms. Each contribution to the bubble energy is parametrized on MD calculations performed in iron. The model is shown to reproduce accurately the dissociation energies obtained by MD over a large range of helium-to-vacancy ratios. Improvements over previous models are shown on a few equilibrium properties: binding energies, solid to fluid transition, helium density in bubbles and validity of Laplace law. Beyond the iron case, such a model should be valid in other metals where helium behavior is similar.}, +@article{rader_verification_2018, + title = {Verification of {Modelica}-{Based} {Models} with {Analytical} {Solutions} for {Tritium} {Diffusion}}, + volume = {203}, + issn = {0029-5450, 1943-7471}, + url = {https://www.tandfonline.com/doi/full/10.1080/00295450.2018.1431505}, + doi = {10.1080/00295450.2018.1431505}, + abstract = {Tritium transport in metal and molten salt fluids combined with diffusion through high-temperature structural materials is an important phenomenon in both magnetic confinement fusion (MCF) and molten salt reactor (MSR) applications. For MCF, tritium is desirable to capture for fusion fuel. For MSRs, uncaptured tritium potentially can be released to the environment. In either application, quantifying the time- and space-dependent tritium concentration in the working fluid(s) and structural components is necessary.}, language = {en}, number = {1}, - urldate = {2019-11-05}, - journal = {Journal of Nuclear Materials}, - author = {Jourdan, T. and Crocombette, J. -P.}, - month = nov, - year = {2011}, - keywords = {Bubble, Molecular Dynamics}, - pages = {98--105}, - file = {Jourdan et Crocombette - 2011 - A variable-gap model for calculating free energies.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PWAI98VP\\Jourdan et Crocombette - 2011 - A variable-gap model for calculating free energies.pdf:application/pdf}, + urldate = {2022-01-24}, + journal = {Nuclear Technology}, + author = {Rader, Jordan D. and Greenwood, M. Scott and Humrickhouse, Paul W.}, + month = jul, + year = {2018}, + pages = {58--65}, + file = {Rader et al. - 2018 - Verification of Modelica-Based Models with Analyti.pdf:D\:\\Logiciels\\data_zotero\\storage\\49SLH59B\\Rader et al. - 2018 - Verification of Modelica-Based Models with Analyti.pdf:application/pdf}, } -@article{wurger_is_2013, - series = {10th {International} {Meeting} on {Thermodiffusion}}, - title = {Is {Soret} equilibrium a non-equilibrium effect?}, - volume = {341}, - issn = {1631-0721}, - url = {http://www.sciencedirect.com/science/article/pii/S1631072113000417}, - doi = {10.1016/j.crme.2013.02.006}, - abstract = {Recent thermophoretic experiments on colloidal suspensions revived an old debate, namely whether the Soret effect is properly described by thermostatics, or necessarily requires non-equilibrium thermodynamics. Based on colloidal transport theory and the entropy production of the related viscous flow, our analysis leads to the conclusion that the equilibrium approach may work for small ions, yet fails for colloidal particles and polymers. Regarding binary molecular mixtures, our results shed some doubt on the validity of thermostatic approaches that derive the Soret coefficient from equilibrium potentials.}, +@article{merrill_modifications_2019, + series = {{SI}:{SOFT}-30}, + title = {Modifications to the {MELCOR}-{TMAP} code to simultaneously treat multiple fusion coolants}, + volume = {146}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379618308135}, + doi = {10.1016/j.fusengdes.2018.12.048}, + abstract = {This paper describes recent progress at Idaho National Laboratory (INL) in developing the MELCOR-TMAP computer code for fusion. The MELCOR-TMAP for fusion computer code is being developed by INL’s Fusion Safety Program (FSP) by modifying the US Nuclear Regulatory Commission’s (NRC’s) MELCOR computer code for fission reactor severe accident analyses. Recently the INL FSP completed the process of merging INL’s Tritium Migration Analysis Program (TMAP) with MELCOR to provide the US fusion community with a more comprehensive tool for analyzing accidents in future fusion reactors. However, prior to the present modifications, a MELCOR-TMAP user could only substitute one of a number of available fusion coolants for MELCOR’s default coolant of water. This new capability corrects this modeling gap needed for safety assessments of fusion reactors that contain more than a single coolant. In this article, we discuss the present code modifications, benchmark MELCOR-TMAP against predictions from previous versions of the MELCOR code, illustrate the application of the code to analysis of an accident in a multiple fluids reactor concept, and describe future plans for the MELCOR-TMAP code.}, language = {en}, - number = {4}, - urldate = {2019-10-17}, - journal = {Comptes Rendus Mécanique}, - author = {Würger, Alois}, - month = apr, - year = {2013}, - pages = {438--448}, - file = {Würger - 2013 - Is Soret equilibrium a non-equilibrium effect.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MH859YQX\\Würger - 2013 - Is Soret equilibrium a non-equilibrium effect.pdf:application/pdf}, + urldate = {2022-01-24}, + journal = {Fusion Engineering and Design}, + author = {Merrill, B. J. and Humrickhouse, P. W. and Yoon, S-J.}, + month = sep, + year = {2019}, + keywords = {Accident analyses, Fusion safety, MELCOR, TMAP, Tritium transport}, + pages = {289--292}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2BISI243\\S0920379618308135.html:text/html}, } -@article{faney_spatially_2015, - title = {Spatially dependent cluster dynamics model of {He} plasma surface interaction in tungsten for fusion relevant conditions}, - volume = {55}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/55/1/013014}, - doi = {10.1088/0029-5515/55/1/013014}, - abstract = {In fusion reactors, plasma facing components (PFC) and, in particular, the divertor will be irradiated with high fluxes of low-energy (∼100 eV) helium and hydrogen ions. Tungsten is one of the leading candidate divertor materials for ITER and DEMO fusion reactors. However, the behaviour of tungsten under high dose, coupled helium/hydrogen exposure remains to be fully understood. The PFC response and performance changes are intimately related to microstructural changes, such as the formation of point defect clusters, helium and hydrogen bubbles or dislocation loops. Computational materials' modelling results are described here that investigate the mechanisms controlling microstructural evolution in tungsten. The aim of this study is to understand and predict sub-surface helium bubble growth under high flux helium ion implantation (∼1022 m−2 s−1) at high temperatures ({\textgreater}1000 K). We report results from a spatially dependent cluster dynamics model based on reaction–diffusion rate theory to describe the evolution of the microstructure under these conditions. The key input parameters to the model (diffusion coefficients, migration and binding energies, initial defect production) are determined from a combination of atomistic modelling and available experimental data. The results are in good agreement with results of an analytical model that is presented in a separate paper. In particular, it is found that the sub-surface evolution with respect to bubble size and concentration of the helium bubbles strongly depends on the flux and temperature.}, - language = {en}, - number = {1}, - urldate = {2019-10-28}, - journal = {Nuclear Fusion}, - author = {Faney, T. and Krasheninnikov, S. I. and Wirth, B. D.}, - year = {2015}, - keywords = {Bubble, Cluster dynamics}, - pages = {013014}, - file = {Faney et al. - 2014 - Spatially dependent cluster dynamics model of He p.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\K7KCEVWB\\Faney et al. - 2014 - Spatially dependent cluster dynamics model of He p.pdf:application/pdf}, +@techreport{fuerst_tritium_2021, + title = {Tritium {Transport} {Phenomena} in {Molten}-{Salt} {Reactors}: {Molten} {Salt} {Tritium} {Transport} {Experiment} {Design}}, + shorttitle = {Tritium {Transport} {Phenomena} in {Molten}-{Salt} {Reactors}}, + url = {https://www.osti.gov/biblio/1828384}, + abstract = {Tritium is produced from neutron interactions with both lithium and beryllium. Large quantities of tritium are generated in Molten Salt Reactors (MSRs) which use LiF/BeF2 (FLiBe) as the fuel salt. Tritium is unique among the radionuclide hazards as it readily permeates through metal structural materials at high temperatures. All metal surfaces are potential release paths for tritium. For adequate safety analysis and eventual licensing of new reactors, predictive models for tritium transport and release from MSRs must be developed. These models must account for the multiple transport phenomena involved with tritium: fuel salt phase mass transport, dissociation/recombination reactions on metal surfaces, interstitial diffusion through the metal structure, and salt or gas phase mass transport in the downstream fluid. These models also must also be validated with representative experiments. Our previous report outlined tritium transport phenomena involved in MSRs, made suggestions on gaps in the transport dataset, and proposed an experimental test stand to test combined transport effects – tritium transport through pipe walls in a convective salt flow. In this report, we summarize an updated analysis framework for tritium transport in MSRs, report our results on hydrogen and deuterium permeation through Hastelloy N, and describe the final design of the Molten Salt Tritium Transport Experiment (MSTTE, pronounced “misty”). The MSRE provides the only wholistic experimental data set for tritium transport in MSRs and understanding the transport phenomena involved in the MSRE is crucial for future model development. One set of parameters in our analysis framework was unknown for the MSRE—surface reaction rates for tritium on Hastelloy N. This warranted our hydrogen and deuterium permeation campaign to assess the permeability, diffusivity, and solubility of hydrogen isotopes in clean Hastelloy N. Surface reaction rate constants were probed by low pressure measurements, however, no surface effects were observed in the limits of our permeation apparatus. Permeation experiments on oxidized Hastelloy N were not performed for this report but are planned in future work. The experimental test stand, MSTTE, measures combined transport properties of the salt-metal system. MSTTE is a forced convection FLiBe loop with custom designed test section to measure tritium transport through candidate structural materials. We use MSRE relevant dimensionless numbers to design and scale the test section. Hastelloy N is a candidate loop and test section material due to the relevance for the MSRE and related designs, however, other metals are being considered (e.g. 316H SS) which may better align with current vendor concepts.}, + language = {English}, + number = {INL/EXT-21-63108-Rev000}, + urldate = {2022-01-24}, + institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)}, + author = {Fuerst, Thomas F. and Taylor, Chase N. and Humrickhouse, Paul W.}, + month = jun, + year = {2021}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DNQNXCCV\\Fuerst et al. - 2021 - Tritium Transport Phenomena in Molten-Salt Reactor.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XNB6IJYL\\1828384.html:text/html}, } -@article{sefta_helium_2013, - title = {Helium bubble bursting in tungsten}, - volume = {114}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.4860315}, - doi = {10.1063/1.4860315}, - number = {24}, - urldate = {2019-10-25}, - journal = {Journal of Applied Physics}, - author = {Sefta, Faiza and Juslin, Niklas and Wirth, Brian D.}, - month = dec, - year = {2013}, - keywords = {Bubble, Bursting}, - pages = {243518}, +@article{woller_impact_2017, + title = {Impact of helium ion energy modulation on tungsten surface morphology and nano-tendril growth}, + volume = {57}, + issn = {0029-5515, 1741-4326}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/aa67ac}, + doi = {10.1088/1741-4326/aa67ac}, + abstract = {Time-modulated helium (He) ion energy (e.g. VBias  =  −50  +  25·sin(2πfRF · t), fRF  =  13.56 MHz) is demonstrated to strongly affect the development of tungsten (W) surface morphology that results from He plasma irradiation in the DIONISOS linear plasma experiment. Nano-tendril bundles (NTBs), which appear as isolated ‘islands’ of nano-tendrils, can rapidly grow on an otherwise smooth W surface. This is in contrast to previously seen full-surface coverage of nano-tendril growth known as ‘fuzz’. When tall NTBs form, less than 15\% of the surface contains nano-tendrils. The NTB surface coverage changes with growth conditions and the total volume of nano-tendrils in the NTBs is observed to be up to a factor of 16 larger than when fuzz is grown. This indicates that long-range W surface transport underlies nano-tendril formation. Surface temperature 870–1220 K, the DC bias potential  −30 to  −70 V, and the ion flux density 4.4  ×  1021–1.1  ×  1022 He · m−2 · s−1 are varied in the experiments. NTBs form at similar conditions as fuzz with the critical difference being the RF modulation of the ion energy bombarding the W, another indication of the importance of W surface transport. Mass loss measurements indicate net erosion with a yield of 1–8  ×  10−4 W/He when NTBs form; erosion that is not attributable to chemical or physical sputtering by He or impurities in the plasma. The erosion is correlated to the NTB growth, based on post-exposure inspection by electron microscopy indicating that NTBs are prone to loss from the surface. NTB growth is compared to the empirical growth-erosion model of fuzz, showing NTBs grow up to a factor of 100 times taller than the expected fuzz layer depth under DC bias conditions. Insights into nano-tendril growth provided by this new growth regime are discussed. Strategies to mitigate W fuzz growth may inadvertently result in rapid localized nano-tendril bundle growth with a higher probability of dust production.}, + language = {en}, + number = {6}, + urldate = {2022-01-24}, + journal = {Nuclear Fusion}, + author = {Woller, K.B. and Whyte, D.G. and Wright, G.M.}, + month = jun, + year = {2017}, + pages = {066005}, + file = {Woller et al. - 2017 - Impact of helium ion energy modulation on tungsten.pdf:D\:\\Logiciels\\data_zotero\\storage\\7MH548QA\\Woller et al. - 2017 - Impact of helium ion energy modulation on tungsten.pdf:application/pdf}, } -@article{miyamoto_microscopic_2011, - series = {Proceedings of the 19th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion}}, - title = {Microscopic damage of tungsten exposed to deuterium–helium mixture plasma in {PISCES} and its impacts on retention property}, - volume = {415}, +@article{raiman_corrosion_2022, + title = {Corrosion of {316H} stainless steel in flowing {FLiNaK} salt}, + volume = {561}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311511000201}, - doi = {10.1016/j.jnucmat.2011.01.008}, - abstract = {Microscopic damage and D retention in tungsten have been investigated for low-energy (∼60–120eV), high flux (∼1022m−2s−1), high fluence (∼5×1025m−2) ion bombardment at moderate temperature (∼573–773K) in mixed species D+He plasmas in the linear divertor plasma simulators PISCES-A and B. A significant reduction in D retention a -nd the formation of nanometer-sized He bubbles occur in W due to seeding of He into the D plasma. The volume fraction of He bubbles, estimated with TEM observations and ellipsometric measurements, exceeds the percolation threshold. The desorption mechanism that injected D atoms diffuse back to the surface through the percolating bubbles is suggested. The seeding of Be into D+He mixture plasma eliminates this He effect on the reduction in D retention.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311522000472}, + doi = {10.1016/j.jnucmat.2022.153551}, + abstract = {Type 316H stainless steel samples were exposed to flowing FLiNaK salt for 1000 h in a monometallic thermal convection loop (TCL) with a maximum temperature of 650 °C and a minimum of 540 °C. Samples in the hottest part of the TCL lost mass, with a maximum mass loss of 1.4 mg/cm2, while samples in the coldest parts of the TCL gained mass, with a maximum mass gain of 1.0 mg/cm2. Analysis of the samples that gained mass showed an Fe-rich layer on the sample surfaces, indicating that Fe, not Cr, was the primary deposition product in the TCL. Cr loss was apparent to a depth of ∼5 µm in the hot leg. Post-exposure analysis of the salt showed major increases in the Cr, Fe, and Mn contents. The TCL was modeled using the TRANSFORM code. Modeled values matched the experimental temperature measurements showing that TRANSFORM is capable of accurately simulating the TCL conditions.}, language = {en}, - number = {1, Supplement}, - urldate = {2019-10-25}, + urldate = {2022-01-23}, journal = {Journal of Nuclear Materials}, - author = {Miyamoto, M. and Nishijima, D. and Baldwin, M. J. and Doerner, R. P. and Ueda, Y. and Yasunaga, K. and Yoshida, N. and Ono, K.}, + author = {Raiman, Stephen S. and Kurley, J. Matthew and Sulejmanovic, Dino and Willoughby, Adam and Nelson, Scott and Mao, Keyou and Parish, Chad M. and Greenwood, M. Scott and Pint, Bruce A.}, + month = apr, + year = {2022}, + keywords = {Corrosion, Fluoride Salt, Molten salt, Molten salt reactor, MSR, Stainless steel}, + pages = {153551}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PV2I3U2I\\S0022311522000472.html:text/html}, +} + +@article{anderl_deuteriumtritium_2004, + series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)}, + title = {Deuterium/tritium behavior in {Flibe} and {Flibe}-facing materials}, + volume = {329-333}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311504003952}, + doi = {10.1016/j.jnucmat.2004.04.220}, + abstract = {Experimental studies to investigate the behavior of deuterium and tritium in the molten salt Flibe (2LiF·BeF2), have been conducted as part of the Japan–US joint research program (JUPITER-II). Measurements of deuterium transport were made in a cylindrically symmetric, dual permeation probe assembly containing 400 cc of Flibe. An exact analytical transport solution in cylindrical coordinates was fit to the measured permeation data, and this analysis derived deuterium diffusion and solubility coefficients of 8.0×10−10 m2/s and 3.1×10−4 mol/m3Pa at 600 °C, respectively, and 3.0×10−9 m2/s and 1.0×10−4 mol/m3Pa at 650 °C. The diffusion coefficients were about a factor of two less than previous results derived from capillary-reservoir diffusion measurements with tritium. Solubility results were significantly greater than previously measured for D2 but they were comparable to those for DF in Flibe. The results suggest that the dominant deuterium transport species in Flibe was D+F− for these experiments.}, + language = {en}, + urldate = {2022-01-21}, + journal = {Journal of Nuclear Materials}, + author = {Anderl, R. A and Fukada, S and Smolik, G. R and Pawelko, R. J and Schuetz, S. T and Sharpe, J. P and Merrill, B. J and Petti, D. A and Nishimura, H and Terai, T and Tanaka, S}, month = aug, - year = {2011}, - keywords = {Bubble, Experiment}, - pages = {S657--S660}, - file = {Miyamoto et al. - 2011 - Microscopic damage of tungsten exposed to deuteriu.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W3P23H4A\\Miyamoto et al. - 2011 - Microscopic damage of tungsten exposed to deuteriu.pdf:application/pdf}, + year = {2004}, + pages = {1327--1331}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\57J3NPFW\\Anderl et al. - 2004 - Deuteriumtritium behavior in Flibe and Flibe-faci.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GYW23JA4\\S0022311504003952.html:text/html}, } -@article{zhou_towards_2010, - title = {Towards suppressing {H} blistering by investigating the physical origin of the {H}–{He} interaction in {W}}, - volume = {50}, - issn = {0029-5515}, - doi = {10.1088/0029-5515/50/11/115010}, - abstract = {We investigate the physical origin of H–He interaction in W in terms of optimal charge density by calculating the energetics and diffusion properties using a first-principles method. On the one hand, we show a strong attraction between H and He in W originated from the charge density redistribution due to the presence of He, driving H segregation towards He. This can block the permeation of H into deeper bulk and thus suppress H blistering. On the other hand, we demonstrate that He, rather than H, energetically prefers to occupy the vacancy centre due to its closed-shell structure, which can block H2 formation at the vacancy centre. This is because He causes a redistribution of charge density inside the vacancy to make it ‘not optimal’ for the formation of H2 molecules, which can be treated as a preliminary nucleation of the H bubbles. We thus propose that H retention and blistering in W can be suppressed by doping the noble gas elements.}, +@incollection{kondo_606_2020, + address = {Oxford}, + title = {6.06 - {Liquid} {Breeder} {Materials}}, + isbn = {978-0-08-102866-7}, + url = {https://www.sciencedirect.com/science/article/pii/B9780128035818116194}, + abstract = {Self-cooled liquid blanket concepts are being studied for both magnetic confinement fusion reactors and inertial fusion reactors. The blanket structures can be simplified according to their multiple function such as a T breeder, a T transporter, a reactor coolant and a shielding material. There are several options for the blanket designs according to the selection of liquid breeder materials. Liquid Li reveals an excellent coolability according to its large heat transfer performance. Liquid Li alloys such as Pb-16Li and Sn-20Li reasonably contain the elements which function as a T breeder and a neutron multiplier. Liquid Pb­16Li is proposed as T breeder of ITER-TBM. Molten fluoride salts such as FLiBe and FLiNaBe have the advantage of chemical inertness and extremely low electrical conductivity which can practically eliminates MHD problems. The common issues of the liquid breeder materials are to clarify their T breeding performance, to control their T transfer behaviors, and to improve their material compatibility with structural and functional materials. This article reviews research findings on nuclear property, physical chemistry and material compatibility of liquid breeder materials.}, language = {en}, - number = {11}, - journal = {Nuclear Fusion}, - author = {Zhou, Hong-Bo and Liu, Yue-Lin and Jin, Shuo and Zhang, Ying and Luo, G.-N. and Lu, Guang-Hong}, - month = oct, - year = {2010}, - keywords = {Bubble, Density Functional Theory, Blistering}, - pages = {115010}, - file = {Zhou et al. - 2010 - Towards suppressing H blistering by investigating .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X29IENDC\\Zhou et al. - 2010 - Towards suppressing H blistering by investigating .pdf:application/pdf}, + urldate = {2022-01-21}, + booktitle = {Comprehensive {Nuclear} {Materials} ({Second} {Edition})}, + publisher = {Elsevier}, + author = {Kondo, Masatoshi and Tanaka, Teruya and Fukada, Satoshi and Valentyn, Tsisar}, + editor = {Konings, Rudy J. M. and Stoller, Roger E.}, + month = jan, + year = {2020}, + doi = {10.1016/B978-0-12-803581-8.11619-4}, + keywords = {Corrosion, Molten salt, Blanket design, Liquid metal, Lithium, Material compatibility, Tritium breeding, Tritium solubility, Tritium transfer}, + pages = {176--202}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\WB8HPG6G\\Kondo et al. - 2020 - 6.06 - Liquid Breeder Materials.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\JTEEHCIK\\B9780128035818116194.html:text/html}, } -@article{morishita_nucleation_2007, - title = {Nucleation path of helium bubbles in metals during irradiation}, - volume = {87}, - issn = {1478-6435}, - url = {https://doi.org/10.1080/14786430601096910}, - doi = {10.1080/14786430601096910}, - abstract = {A thermodynamic formalization is developed for description of the nucleation and growth of helium bubbles in metals during irradiation. The proposed formalization is available for evaluating both microstructural changes in fusion first wall materials where helium is produced by (n, α) nuclear transmutation reactions, and those in fusion diverter materials where helium particles with low energy are directly implanted. The calculated nucleation barrier is significantly reduced by the presence of helium, showing that a helium bubble with an appropriate number of helium atoms depending on bubble size can nucleate without any large nucleation barriers, even at a condition where an empty void has very large nucleation barriers without helium. With the proposed thermodynamic formalization, the nucleation and growth process of helium bubbles in iron during irradiation is simulated by the kinetic Monte Carlo (KMC) technique. It shows the nucleation path of a helium bubble on the (N He, N V) space as functions of temperatures and the concentration of helium in the matrix, where N He and N V are the numbers of helium atoms and vacancies contained in the helium bubble, respectively. Bubble growth rates depend on the nucleation path and suggest that two different mechanisms operate for bubble growth: one is controlled by vacancy diffusion and the other is controlled by interstitial helium diffusion.}, - number = {7}, - urldate = {2019-10-31}, - journal = {Philosophical Magazine}, - author = {Morishita, K.}, - month = mar, - year = {2007}, - keywords = {Bubble, Monte Carlo}, - pages = {1139--1158}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\68FG98DG\\14786430601096910.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Y792FZS8\\Morishita - 2007 - Nucleation path of helium bubbles in metals during.pdf:application/pdf}, +@article{lam_impact_2021, + title = {The impact of hydrogen valence on its bonding and transport in molten fluoride salts}, + volume = {9}, + issn = {2050-7488, 2050-7496}, + url = {http://xlink.rsc.org/?DOI=D0TA10576G}, + doi = {10.1039/D0TA10576G}, + abstract = {In molten fluoride salt systems, the chemistry and transport of hydrogen are coupled to its valence state, which controls the balance of tritium leakage and corrosion. + , + + Interest in molten salts has increased significantly over the last decade due to their potential application in various clean-energy technologies including hydrogen generation, solar heat storage, advanced fission nuclear power plants, and compact fusion energy systems. In nuclear fission and fusion power plants, high heat capacity molten salts allow operation at high temperature and atmospheric pressure, which could dramatically increase efficiency, reduce capital cost, and enable passive safety features. In many of these systems, the hydrogen isotope is of particular importance due to its ability to corrode structural materials as + 3 + H + + + in fluoride salts, and its potential to cause significant radioactive release as diffusive + 3 + H + 0 + , which are cited as key barriers to technological deployment. Yet, the chemistry and transport behavior of the hydrogen species remain poorly understood due to the difficulties in handling toxic salts and radioactive materials. Here, using + ab initio + molecular dynamics, we present a coupled examination of hydrogen speciation in the most common prototypical salts 66.6\% LiF–33.3\% BeF + 2 + (Flibe) and 46.5\% LiF–11.5\% NaF–42\% KF (Flinak). Using extensively validated calculations on the local structure and dynamics, we find significant difference between + 3 + H + 0 + and + 3 + H + + + transport behaviors that are usually overlooked. We find that + 3 + H + 0 + , which always exists as H + 2 + , diffuses 3–5 times faster than + 3 + H + + + , which can be ascribed to hydrogen bonding and complexation in solution. This work explains contradicting experimental results and provides useful species transport data for designing hydrogen capture and corrosion control systems for molten salts.}, + language = {en}, + number = {3}, + urldate = {2022-01-21}, + journal = {Journal of Materials Chemistry A}, + author = {Lam, Stephen T. and Li, Qing-Jie and Mailoa, Jonathan and Forsberg, Charles and Ballinger, Ronald and Li, Ju}, + year = {2021}, + pages = {1784--1794}, + annote = {MD study of T+ implantation in Flinak and FLiBe +  +In Flinak, H+ is mainly (90\%) present in the HF2 form. +In Flibe, H+ is mainly (50\%) present in the HF form. +  + }, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HE2H5H4D\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf;Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:D\:\\Logiciels\\data_zotero\\storage\\YN7LXZJM\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BV2BZKQY\\d0ta10576g.html:text/html;Supplementary Information PDF:D\:\\Logiciels\\data_zotero\\storage\\UYDU9QAG\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf}, } -@article{myers_ion_1985, - series = {Proceedings of the {International} {Conference} on {Surface} {Modification} of {Metals} by {Ion} {Beams}}, - title = {Ion beam studies of hydrogen in metals}, - volume = {69}, - issn = {0025-5416}, - url = {http://www.sciencedirect.com/science/article/pii/0025541685903398}, - doi = {10.1016/0025-5416(85)90339-8}, - abstract = {Methods based on ion implantation and nuclear reaction analysis have been developed and used to investigate fundamental aspects of the behavior of hydrogen isotopes in metals. The binding enthalpy of deuterium at irradiation defects, helium bubbles, deuterium bubbles and metal-oxide interfaces was measured for aluminum, iron, nickel, copper, palladium, austenitic stainless steel, Inconel and amorphous Fe40Ni40P14B6. The binding enthalpies determined for the pure metals are in excellent agreement with mechanistic calculations based on effective medium theory and other information. Surface-limited release of deuterium from iron, stainless steel and Inconel was measured as a function of temperature and the state of surface oxidation. The release rate was accurately proportional to the square of the deuterium concentration in solution, permitting the results to be expressed in terms of a surface recombination coefficient. This quantity was up to four orders of magnitude greater for an ion-sputtered surface than for a surface with electropolish oxide. The diffusion coefficient and solid solubility of tritium in stainless steel were measured for the first time at the ice point, thereby extending downward by three orders of magnitude the diffusivities available from conventional permeation experiments. Deuterium concentration profiles resulting from electrochemical charging of Incology 903 were measured as a function of charging current, thereby providing a direct systematic calibration of such charging in an austenitic material where conventional permeation measurements are precluded by the small hydrogen diffusion rate.}, +@misc{noauthor_deuteriumtritium_nodate, + title = {Deuterium/tritium behavior in {Flibe} and {Flibe}-facing materials - {ScienceDirect}}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311504003952?via%3Dihub}, + urldate = {2022-01-21}, + file = {Deuterium/tritium behavior in Flibe and Flibe-facing materials - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\4MDAIMLS\\S0022311504003952.html:text/html}, +} + +@article{fukada_hydrogen_2006, + title = {Hydrogen permeability through a mixed molten salt of {LiF}, {NaF} and {KF} ({Flinak}) as a heat-transfer fluid}, + volume = {358}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311506004089}, + doi = {10.1016/j.jnucmat.2006.07.011}, + abstract = {Permeability, diffusivity and solubility of hydrogen in Flinak, a mixed molten salt of LiF (46.5\%), NaF (11.5\%) and KF (42\%), were determined using a vessel supported by a Ni plate. Diffusion-limiting permeation was confirmed by experimental data where hydrogen permeation rates were in reverse proportion to the thickness of Flinak. Diffusivities determined in the range of 500–750°C were correlated to an Arrhenius equation with the activation energy of 50kJ/mol. Since the dependence of hydrogen solubility in Flinak on pressure was almost linear, hydrogen was dissolved as H2 in Flinak. The H2 solubility in Flinak was correlated to a Henry law, and its solubility constant was discussed in terms of macroscopic surface tension and unspecified interaction energy between the molten salt and dissolved gaseous molecules.}, language = {en}, number = {2}, - urldate = {2019-11-05}, - journal = {Materials Science and Engineering}, - author = {Myers, S. M. and Wampler, W. R. and Besenbacher, F. and Robinson, S. L. and Moody, N. R.}, - month = mar, - year = {1985}, - keywords = {Experiment}, - pages = {397--409}, - file = {Myers et al. - 1985 - Ion beam studies of hydrogen in metals.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EC7QR6UK\\Myers et al. - 1985 - Ion beam studies of hydrogen in metals.pdf:application/pdf}, + urldate = {2022-01-21}, + journal = {Journal of Nuclear Materials}, + author = {Fukada, Satoshi and Morisaki, Akio}, + month = nov, + year = {2006}, + pages = {235--242}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\I28NCMQV\\Fukada et Morisaki - 2006 - Hydrogen permeability through a mixed molten salt .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PLDNDRA6\\S0022311506004089.html:text/html}, } -@article{iwakiri_effects_2002, - title = {Effects of helium bombardment on the deuterium behavior in tungsten}, - volume = {307-311}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311502011789}, - doi = {10.1016/S0022-3115(02)01178-9}, - abstract = {The effects of pre-irradiation with helium ions of fusion relevant energy on trapping of injected deuterium in W was studied by thermal desorption spectrometry technique using high-resolution quadrupole mass spectrometer. Pre-irradiation with He ions caused remarkable effects on the trapping of injected deuterium. Most of the injected deuterium is desorbed between 400 and 600 K for the case without helium pre-irradiation, while additional desorption occurs between 600 and 800 K for the helium pre-irradiation case. Total amount of the trapped deuterium for irradiations of 2.0×1021 He/m2 and 1.0×1022 D2/m2 is 6.2×1020 D2/m2, which is more than three times higher than that in the case of no helium pre-irradiation. The present result indicates that irradiation effects of He bombardment must be taken into account to understand and evaluate the behavior of hydrogen isotopes in fusion environment.}, +@article{rota_measurements_1982, + title = {Measurements of surface and bulk properties for the interaction of hydrogen with inconel 600}, + volume = {111-112}, + issn = {00223115}, + url = {https://linkinghub.elsevier.com/retrieve/pii/0022311582902148}, + doi = {10.1016/0022-3115(82)90214-8}, language = {en}, - urldate = {2019-11-04}, + urldate = {2022-01-21}, journal = {Journal of Nuclear Materials}, - author = {Iwakiri, H. and Morishita, K. and Yoshida, N.}, - month = dec, - year = {2002}, - keywords = {Experiment}, - pages = {135--138}, - file = {Iwakiri et al. - 2002 - Effects of helium bombardment on the deuterium beh.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\K946CAHJ\\Iwakiri et al. - 2002 - Effects of helium bombardment on the deuterium beh.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HWM3T2A9\\S0022311502011789.html:text/html}, + author = {Rota, E. and Waelbroeck, F. and Wienhold, P. and Winter, J.}, + month = nov, + year = {1982}, + pages = {233--239}, + annote = {Study on inconel600 (aka A600) +Diffusion coefficients of H and D +Solubility coefficient (sieverts) +  +Recombination coefficients +Dissociation coefficients +  +}, + file = {Rota et al. - 1982 - Measurements of surface and bulk properties for th.pdf:D\:\\Logiciels\\data_zotero\\storage\\U62D5GXG\\Rota et al. - 1982 - Measurements of surface and bulk properties for th.pdf:application/pdf}, } -@article{henriksson_depths_2006, - title = {The {Depths} of {Hydrogen} and {Helium} {Bubbles} in {Tungsten}: {A} {Comparison}}, - volume = {50}, - issn = {1536-1055}, - shorttitle = {The {Depths} of {Hydrogen} and {Helium} {Bubbles} in {Tungsten}}, - url = {https://doi.org/10.13182/FST06-A1219}, - doi = {10.13182/FST06-A1219}, - abstract = {The role of self-trapping and defect trapping of hydrogen and helium implanted into tungsten has been investigated using density functional theory (DFT) calculations, molecular dynamics simulations, and kinetic Monte Carlo simulations (KMCSs). The potential energy curves of hydrogen or helium pairs were obtained by molecular dynamics, and the energy of the most essential states was checked with DFT. Under assumptions of bubble formation due to trapping by similiar impurity atoms (self-trapping) or defects, KMCSs were carried out using parameters from implantation experiments. The results indicate that self-trapping plays no (or a very small) role in hydrogen bubble formation, whereas helium bubbles form due to strong self-trapping.}, - number = {1}, - urldate = {2019-11-05}, - journal = {Fusion Science and Technology}, - author = {Henriksson, K. O. E. and Nordlund, K. and Krasheninnikov, A. and Keinonen, J.}, - month = jul, - year = {2006}, - keywords = {Bubble, Density Functional Theory, Monte Carlo}, - pages = {43--57}, - file = {Henriksson et al. - 2006 - The Depths of Hydrogen and Helium Bubbles in Tungs.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5LPBPBIY\\Henriksson et al. - 2006 - The Depths of Hydrogen and Helium Bubbles in Tungs.pdf:application/pdf}, +@article{bai_efficient_2010, + title = {Efficient {Annealing} of {Radiation} {Damage} {Near} {Grain} {Boundaries} via {Interstitial} {Emission}}, + volume = {327}, + issn = {0036-8075, 1095-9203}, + url = {https://www.science.org/doi/10.1126/science.1183723}, + doi = {10.1126/science.1183723}, + language = {en}, + number = {5973}, + urldate = {2022-01-05}, + journal = {Science}, + author = {Bai, Xian-Ming and Voter, Arthur F. and Hoagland, Richard G. and Nastasi, Michael and Uberuaga, Blas P.}, + month = mar, + year = {2010}, + pages = {1631--1634}, + file = {Bai et al. - 2010 - Efficient Annealing of Radiation Damage Near Grain.pdf:D\:\\Logiciels\\data_zotero\\storage\\BR6YTNKT\\Bai et al. - 2010 - Efficient Annealing of Radiation Damage Near Grain.pdf:application/pdf}, } -@article{lee_hydrogen_2007, - series = {Plasma-{Surface} {Interactions}-17}, - title = {Hydrogen and helium trapping in tungsten under simultaneous irradiations}, - volume = {363-365}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311507001754}, - doi = {10.1016/j.jnucmat.2007.01.111}, - abstract = {Hydrogen and helium trapping in polycrystalline tungsten under simultaneous He+–H+ and He+–D+ irradiation was measured by thermal desorption spectroscopy. At 300K: He retention and release are affected very little by the presence of H, closely following He+-only irradiations; He is trapped within ∼30nm of the surface. D retention is similar to D+-only levels but the presence of He enhances D trapping in the near surface, while limiting D diffusion into the bulk; D is trapped within ∼30–35nm of the surface possibly at interstitial sites surrounding He–vacancy defects. At 700K: He retention and release are again similar to He+-only cases; He is trapped within ∼30nm of the surface while no D is observed.}, +@article{zhou_simultaneous_2019, + title = {A simultaneous corrosion/irradiation facility for testing molten salt-facing materials}, + volume = {440}, + issn = {0168-583X}, + url = {https://www.sciencedirect.com/science/article/pii/S0168583X18306700}, + doi = {10.1016/j.nimb.2018.11.024}, + abstract = {Aside from the historical Molten Salt Reactor Experiment, a few in-reactor loops, and one electron irradiation/corrosion facility, dedicated facilities to test the combined effects of molten salt corrosion and irradiation on materials do not currently exist. A major gap therefore exists in rapid, reactor-relevant materials testing capabilities which, if remedied, would greatly hasten molten salt reactor development. We present a new accelerator-based facility for rapid, simultaneous testing of molten salt-facing materials utilizing a proton beam as the radiation source. Introducing proton irradiation to a molten salt corrosion system poses specific engineering concerns in sample and corrosion cell design, operational stability, integration with the accelerator beamline, and radiation safety. This paper describes how these requirements were fulfilled with confirmatory tests and results.}, language = {en}, - urldate = {2019-11-05}, - journal = {Journal of Nuclear Materials}, - author = {Lee, H. T. and Haasz, A. A. and Davis, J. W. and Macaulay-Newcombe, R. G. and Whyte, D. G. and Wright, G. M.}, - month = jun, - year = {2007}, - keywords = {Experiment}, - pages = {898--903}, - file = {Lee et al. - 2007 - Hydrogen and helium trapping in tungsten under sim.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6M9LWVWJ\\Lee et al. - 2007 - Hydrogen and helium trapping in tungsten under sim.pdf:application/pdf}, + urldate = {2022-01-05}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Zhou, Weiyue and Woller, Kevin B. and Zheng, Guiqiu (Tony) and Stahle, Peter W. and Short, Michael P.}, + month = feb, + year = {2019}, + keywords = {Corrosion, Molten salt, Radiation}, + pages = {54--59}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZVPNSAJQ\\S0168583X18306700.html:text/html}, +} + +@article{forsberg_fusion_2020, + title = {Fusion {Blankets} and {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} with {Flibe} {Salt} {Coolant}: {Common} {Challenges}, {Tritium} {Control}, and {Opportunities} for {Synergistic} {Development} {Strategies} {Between} {Fission}, {Fusion}, and {Solar} {Salt} {Technologies}}, + volume = {206}, + issn = {0029-5450}, + shorttitle = {Fusion {Blankets} and {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} with {Flibe} {Salt} {Coolant}}, + url = {https://doi.org/10.1080/00295450.2019.1691400}, + doi = {10.1080/00295450.2019.1691400}, + abstract = {Recent developments in high-magnetic-field fusion systems have created large incentives to develop flibe (Li2BeF4) salt fusion blankets that have four functions: (1) convert the high energy of fusion neutrons into heat for the power system, (2) convert lithium into tritium—the fusion fuel, (3) shield the magnets against radiation, and (4) cool the first wall that separates the plasma from the salt blanket. Flibe is the same coolant proposed for fluoride-salt-cooled high-temperature reactors that use clean flibe coolant and graphite-matrix coated-particle fuel. Flibe is also the coolant proposed for some molten salt reactors (MSRs) where the fuel is dissolved in the coolant. The multiple applications for flibe as a coolant create large incentives for cooperative fusion-fission programs for development of the underlying science, design tools, technology (pumps, instrumentation, salt purification, materials, tritium removal, etc.), and supply chains. Other high-temperature molten salts are being developed for alternative MSR systems and for advanced Gen-III concentrated solar power (CSP) systems. The overlapping characteristics of flibe salt with these other salt systems create significant incentives for cooperative fusion-fission-solar programs in multiple areas.We describe the fission and fusion flibe-cooled systems, what has created this synergism, what is different and the same between fission and fusion in terms of using flibe, and the common challenges. We review (1) the characteristics of flibe salts, (2) the status of the technology, (3) the options for tritium capture and control in the salt, heat exchangers, and secondary heat transfer loops, and (4) the coupling to power cycles with heat storage. The technology overlap between flibe systems and other high-temperature MSR and CSP salt systems is described. This defines where there are opportunities for cooperative programs across fission, fusion, and CSP salt programs.}, + number = {11}, + urldate = {2022-01-04}, + journal = {Nuclear Technology}, + author = {Forsberg, Charles and Zheng, Guiqiu (Tony) and Ballinger, Ronald G. and Lam, Stephen T.}, + month = nov, + year = {2020}, + note = {Publisher: Taylor \& Francis +\_eprint: https://doi.org/10.1080/00295450.2019.1691400}, + keywords = {flibe salt, fluoride-salt-cooled high-temperature reactor, fusion, molten salt reactor, Salt-cooled reactors}, + pages = {1778--1801}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XE4HZVFD\\Forsberg et al. - 2020 - Fusion Blankets and Fluoride-Salt-Cooled High-Temp.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\S6FCKS69\\00295450.2019.html:text/html}, } -@article{ueda_simultaneous_2009, - series = {Fusion {Reactor} {Materials}}, - title = {Simultaneous irradiation effects of hydrogen and helium ions on tungsten}, - volume = {386-388}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311508009690}, - doi = {10.1016/j.jnucmat.2008.12.300}, - abstract = {Simultaneous irradiation effects of He on tungsten blistering with hydrogen and carbon mixed ion irradiation were investigated. It was found that only 0.1\% addition of He ions to 1keV H and C mixed ion beam (C: 0.8–1.0\%) reduced (473K) or completely suppressed (653K and 723K) blister formation. According to TEM observation, He bubbles with the size of 2nm or less were formed near the surface, which could be a diffusion barrier of hydrogen into the bulk due to the reduction of diffusion channel or excitation of stress field, leading to the reduction of diffusivity of hydrogen. The reduction rate of hydrogen inward flux by simultaneous He irradiation in our experimental conditions would be more than the factor of three.}, +@article{zeng_behavior_2019, + title = {Behavior characteristics of hydrogen and its isotope in molten salt of {LiF}-{NaF}-{KF} ({FLiNaK})}, + volume = {51}, + issn = {1738-5733}, + url = {https://www.sciencedirect.com/science/article/pii/S1738573318301967}, + doi = {10.1016/j.net.2018.10.008}, + abstract = {Experimental studies to investigate the behaviors of hydrogen in molten FLiNaK (LiF-NaF-KF) have been conducted at 500–700 °C. On the basis of previous studies, the diffusivity and solubility of hydrogen in FLiNaK have been revised, and the expressions can be correlated to the following Arrhenius equations: DH2 = 1.62 × 10−5exp (−48.20 × 103/Rg·T) [m2/s] and SH2 = 1.03 × 10−4exp (−14.96 × 103/Rg·T) [mol-H2/m3/Pa], respectively. The behavior characteristics of deuterium in FLiNaK were studied and compared with the hydrogen behaviors in FLiNaK. The results showed the behaviors of deuterium were consistence with the behaviors of hydrogen in FLiNaK. The difference between hydrogen and deuterium has not been observed upon the experimental research of the behavior characteristics of hydrogen and deuterium in FLiNaK, which suggested the results obtained here might apply equally to the behavior characteristics of tritium in FLiNaK.}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Ueda, Y. and Fukumoto, M. and Yoshida, J. and Ohtsuka, Y. and Akiyoshi, R. and Iwakiri, H. and Yoshida, N.}, + number = {2}, + urldate = {2022-01-04}, + journal = {Nuclear Engineering and Technology}, + author = {Zeng, Youshi and Liu, Wenguan and Liu, Wei and Qian, Yuan and Qian, Nan and Wu, Xiaoling and Huang, Yu and Wu, Shengwei and Wang, Guanghua}, month = apr, - year = {2009}, - keywords = {Experiment}, - pages = {725--728}, - file = {Ueda et al. - 2009 - Simultaneous irradiation effects of hydrogen and h.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8GZVVZND\\Ueda et al. - 2009 - Simultaneous irradiation effects of hydrogen and h.pdf:application/pdf}, -} + year = {2019}, + keywords = {Hydrogen, Deuterium, Diffusion, Permeation, Molten FLiNaK}, + pages = {490--494}, + annote = {Permeation studies with FLiNak (a particular type?) +  -@article{baldwin_effect_2011, - title = {Effect of {He} on {D} retention in {W} exposed to low-energy, high-fluence ({D}, {He}, {Ar}) mixture plasmas}, - volume = {51}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/51/10/103021/meta}, - doi = {10.1088/0029-5515/51/10/103021}, - abstract = {W targets are exposed at fixed temperature in the range ∼420–1100 K, to either pure D2, D2–δHe (0.1 {\textless} δ {\textless} 0.25), or D2–δHe–γAr (γ = 0.03) mixture plasma, or He pretreatment plasma followed by exposure to D2 plasma. A strong reduction in D retention is found for exposure temperature above 450 K and incident He-ion fluence exceeding ∼1024 m−2. Reduced D retention values lie well below that measured on D2 plasma-exposed reference targets, and the scatter in retention values reported in the literature. A small level of Ar admixture to D2–0.1He plasma, leading to an Ar ion density fraction of ∼3\%, is found to have minimal effect on the D inventory reduction caused by He. In targets with reduced inventory, nuclear-reaction analysis reveals shallow D trapping ({\textless}50 nm), in the same locale as nanometre-sized bubbles observed using transmission electron microscopy. It is suggested that near-surface bubbles grow and interconnect, forming pathways leading back to the plasma–material interaction surface, thereby interrupting transport to the bulk and reducing D retention.}, - language = {en}, - number = {10}, - urldate = {2019-11-04}, - journal = {Nuclear Fusion}, - author = {Baldwin, M. J. and Doerner, R. P. and Wampler, W. R. and Nishijima, D. and Lynch, T. and Miyamoto, M.}, - month = aug, - year = {2011}, - keywords = {Experiment}, - pages = {103021}, - file = {Baldwin et al. - 2011 - Effect of He on D retention in W exposed to low-en.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UCW4HSDR\\Baldwin et al. - 2011 - Effect of He on D retention in W exposed to low-en.pdf:application/pdf}, +This idea is to inject H2 (or D2) either at the salt side or at the metal side an measure the permeation flux. +  +CAREFUL THERE'S A MIXUP IN THE STUDIES +}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9VVKKZZR\\S1738573318301967.html:text/html}, } -@article{grigorev_mobility_2016, - title = {Mobility of hydrogen-helium clusters in tungsten studied by molecular dynamics}, - volume = {474}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311516300952}, - doi = {10.1016/j.jnucmat.2016.03.022}, - abstract = {Tungsten is a primary candidate material for plasma facing components in fusion reactors. Interaction of plasma components with the material is unavoidable and will lead to degradation of the performance and the lifetime of the in-vessel components. In order to gain better understanding the mechanisms driving the material degradation at atomic level, atomistic simulations are employed. In this work we study migration, stability and self-trapping properties of pure helium and mixed helium-hydrogen clusters in tungsten by means of molecular dynamics simulations. We test two versions of an embedded atom model interatomic potential by comparing it with ab initio data regarding the binding properties of He clusters. By analysing the trajectories of the clusters during molecular dynamics simulations at finite temperatures we obtain the diffusion parameters. The results show that the diffusivity of mixed clusters is significantly lower, than that of pure helium clusters. The latter suggest that the formation of mixed clusters during mixed hydrogen helium plasma exposure will affect the helium diffusivity in the material.}, +@article{song_tritium_2010, + series = {Proceedings of the {Ninth} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, + title = {Tritium analysis of fusion-based hydrogen production reactor {FDS}-{III}}, + volume = {85}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379610000098}, + doi = {10.1016/j.fusengdes.2010.01.008}, + abstract = {A dynamic subsystem model of tritium fuel cycle for the FDS-III was developed, and the required minimum tritium supply for reactor startup and the doubling time for tritium breeding were calculated by using the Tritium Analysis Software (TAS). Some factors which would affect the tritium supply and doubling time were considered, such as the tritium fractional burnup in the plasma, tritium breeding ratio (TBR), the residence time of tritium in all subsystems, and tritium decay, etc. The results showed that the minimum tritium supply for startup was sensitive with the tritium fractional burnup in the plasma, but the effect of the TBR could be neglected. The double time for tritium breeding strongly depended on the TBR and the tritium fractional burnup. Based on the model, the analysis results predicted that the required initial minimum tritium supply was ∼9.9kg for startup. After one year's operation, the total tritium inventory in fuel cycle system was ∼33kg. And the total tritium release into environment was ∼4mg, which was much lower than the allow level, i.e. 1g-T/year. The tritium in fuel storage system would be doubled and could be extracted to supply for the other fusion power reactor's startup after ∼886days operation.}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Grigorev, Petr and Terentyev, Dmitry and Bonny, Giovanni and Zhurkin, Evgeny E. and van Oost, Guido and Noterdaeme, Jean-Marie}, - month = jun, - year = {2016}, - keywords = {Molecular Dynamics}, - pages = {143--149}, - file = {Grigorev et al. - 2016 - Mobility of hydrogen-helium clusters in tungsten s.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RGML8V9B\\Grigorev et al. - 2016 - Mobility of hydrogen-helium clusters in tungsten s.pdf:application/pdf}, + number = {7}, + urldate = {2021-12-27}, + journal = {Fusion Engineering and Design}, + author = {Song, Yong and Huang, Qunying and Ni, Muyi}, + month = dec, + year = {2010}, + keywords = {Fusion reactor, High temperature blanket, Tritium management}, + pages = {1044--1047}, } -@article{grigorev_molecular_2018, - title = {Molecular dynamics simulation of hydrogen and helium trapping in tungsten}, - volume = {508}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311518301818}, - doi = {10.1016/j.jnucmat.2018.05.052}, - abstract = {Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material for plasma-facing components for future fusion reactors. Interaction of plasma components with the material leads to degradation of the performance and thus the lifetime of the in-vessel components. On top of that special attention is drawn to tritium retention in the reactors vessel from a safety point of view, since tritium is radioactive material. In order to gain better understanding of the mechanisms driving accumulation of plasma components in the material and subsequent degradation of the material, atomistic simulations are employed. The focus of this work is on so-called self trapping of H and He atoms or, in other words, Frenkel pair formation in bulk tungsten in the presence of H and He atoms. Two versions of a model embedded atom interatomic potential and a bond order potential were tested by comparing it with ab initio data regarding the binding properties of pure He and He-H-Vacancy clusters and energetics of Frenkel pair formation. As a result of Molecular Dynamics simulations at finite temperature, the values of critical H concentration needed for the generation of a Frenkel pair in the presence of He clusters were obtained. The results show that the critical H concentration decreases with the size of He cluster present in the simulation cell and thus, Frenkel pair formation by H is facilitated in the presence of He clusters in the material.}, +@article{deng_tritium_2011, + title = {Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention}, + volume = {51}, + issn = {0029-5515, 1741-4326}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/51/7/073041}, + doi = {10.1088/0029-5515/51/7/073041}, + abstract = {New simulation results are predicted in a fusion reactor operation process. They are somewhat similar to, but quite different from, the xenon poisoning effects resulting from fission-produced iodine during the restart-up process of a fission reactor. We obtained completely new results of tritium well depth and tritium well time in magnetic confinement fusion energy research area. This study is carried out to investigate the following: what will be the least amount of tritium storage required to start up a fusion reactor and how long the fusion reactor needs to be operated for achieving the tritium break-even during the initial start-up phase due to the finite tritium-breeding time, which is dependent on the tritium breeder, specific structure of the breeding zone, layout of the coolant flow pipes, tritium recovery scheme and applied extraction process, the tritium retention of plasma facing component (PFC) and other reactor components, unrecoverable tritium fraction in the breeder, leakage to the inertial gas container and the natural radioactive decay time constant. We describe these new issues and answer these problems by setting up and solving a set of equations, which are described by a dynamic subsystem model of tritium inventory evolution in a fusion experimental breeder (FEB). Reasonable results are obtained using our simulation model. It is found that the tritium well depth is about 0.319 kg and the tritium well time is approximately 235 full power operation days for the reference case of the designed FEB configuration, and it is also found that after one-year operation the tritium storage reaches 0.767 kg, which is more than the least amount of tritium storage required to start up another FEB-like fusion reactor. The results show that the tritium retention in the PFC is equivalent to 11.9\% of tritium well depth that is fairly consistent with the result of 10–20\% deduced from the integrated particle balance of European tokamaks. Based on our experimental and theoretical studies, some new mechanisms are proposed for reducing the tritium retention in PFC and structure materials of tritium-breeding blanket. In this paper, a qualitative analysis of the ‘sponge effect’ is carried out. The ‘sponge effect’ may help us to reduce tritium retention by ∼20\% in the PFC.}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Grigorev, Petr and Zinovev, Aleksandr and Terentyev, Dmitry and Bonny, Giovanni and Zhurkin, Evgeny E. and Van Oost, Guido and Noterdaeme, Jean-Marie}, - month = sep, - year = {2018}, - keywords = {Molecular Dynamics}, - pages = {451--458}, - file = {Grigorev et al. - 2018 - Molecular dynamics simulation of hydrogen and heli.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S3XRPWTA\\Grigorev et al. - 2018 - Molecular dynamics simulation of hydrogen and heli.pdf:application/pdf}, + number = {7}, + urldate = {2021-12-27}, + journal = {Nuclear Fusion}, + author = {Deng, B.Q. and Li, Z.X. and Li, C.Y. and Feng, K.M.}, + month = jul, + year = {2011}, + pages = {073041}, + file = {Deng et al. - 2011 - Tritium well depth, tritium well time and sponge m.pdf:D\:\\Logiciels\\data_zotero\\storage\\NFGSJCQ3\\Deng et al. - 2011 - Tritium well depth, tritium well time and sponge m.pdf:application/pdf}, } -@article{shimada_tritium_2017, - series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, - title = {Tritium decay helium-3 effects in tungsten}, - volume = {12}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179116302095}, - doi = {10.1016/j.nme.2016.11.006}, - abstract = {Tritium (T) implanted by plasmas diffuses into bulk material, especially rapidly at elevated temperatures, and becomes trapped in neutron radiation-induced defects in materials that act as trapping sites for the tritium. The trapped tritium atoms will decay to produce helium-3 (3He) atoms at a half-life of 12.3 years. 3He has a large cross section for absorbing thermal neutrons, which after absorbing a neutron produces hydrogen (H) and tritium ions with a combined kinetic energy of 0.76 MeV through the 3He(n,H)T nuclear reaction. The purpose of this paper is to quantify the 3He produced in tungsten by tritium decay compared to the neutron-induced helium-4 (4He) produced in tungsten. This is important given the fact that helium in materials not only creates microstructural damage in the bulk of the material but alters surface morphology of the material effecting plasma-surface interaction process (e.g. material evolution, erosion and tritium behavior) of plasma-facing component materials. Effects of tritium decay 3He in tungsten are investigated here with a simple model that predicts quantity of 3He produced in a fusion DEMO FW based on a neutron energy spectrum found in literature. This study reveals that: (1) helium-3 concentration was equilibrated to ∼6\% of initial/trapped tritium concentration, (2) tritium concentration remained approximately constant (94\% of initial tritium concentration), and (3) displacement damage from 3He(n,H)T nuclear reaction became {\textgreater}1 dpa/year in DEMO FW.}, +@article{liu_analysis_2020, + title = {Analysis of the whole process tritium transport based on fuel cycle modeling for {CFETR}}, + volume = {161}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379620306086}, + doi = {10.1016/j.fusengdes.2020.112060}, + abstract = {Tritium self-sustain is crucial for the successful operation of China Fusion Engineering Test Reactor (CFETR). In this work, tritium fuel cycle model is developed based on the practical tritium plant. The retention values caused by different purification technology which can’t be extracted during the fuel cycle is considered in several sub-systems like Isotope Separation System-Inner cycle(ISS-I). The typical inventory in each sub-system is calculated which resulting that the minimum initial startup inventory (Im) is about 3131 g and tritium breeding ratio that required to satisfy tritium self-sustain (TBRreq) is about 1.13 under typical parameters. The sensitivity relation of Im and TBRreq are analyzed. We found that the fractional burnup is a key factor to affect both.}, language = {en}, - urldate = {2020-12-08}, - journal = {Nuclear Materials and Energy}, - author = {Shimada, M. and Merrill, B. J.}, - month = aug, - year = {2017}, - keywords = {Helium-3, Neutron-irradiation, Plasma facing-components, Tritium}, - pages = {699--702}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IPP2S233\\Shimada et Merrill - 2017 - Tritium decay helium-3 effects in tungsten.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DU4YVBFU\\S2352179116302095.html:text/html}, + urldate = {2021-12-27}, + journal = {Fusion Engineering and Design}, + author = {Liu, Linzi and Tong, Ruihai and Cai, Jinguang and Yao, Yong and Song, Jiangfeng and Chen, Chang’an and Luo, Deli and Yao, Weizhi}, + month = dec, + year = {2020}, + keywords = {Mean residence time, Tritium fuel cycle modeling, Tritium self-sustain}, + pages = {112060}, } -@article{wan_hydrogen_2018, - title = {Hydrogen trapping in helium-implanted {W} and {W}-{Ta} alloy: {First}-principles approach}, - volume = {508}, - issn = {0022-3115}, - shorttitle = {Hydrogen trapping in helium-implanted {W} and {W}-{Ta} alloy}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311518300060}, - doi = {10.1016/j.jnucmat.2018.05.050}, - abstract = {We reveal the interaction of H with He in pure W and W-Ta alloy based on first-principles calculations. We show a strong attraction between H and He in both systems that drives H segregation towards He. The substitutional He and tetrahedral interstitial H defects in W-Ta alloy are more energetically favorable than pure W due to the decreased electronic density of the replaced Ta atom. Moreover, 1 He-Vac complex in both systems can trap as many as 12 H atoms. Based on the calculated formation energy of Hn-He-Vac complexes, the H3-He-Vac has the lowest formation energy in both systems. We believe that such understanding is generally applicable for H bubble formation in metals and metal alloys.}, +@misc{day_tritium_2016, + title = {Tritium fuel cycle and self-sufficiency - {R}\&{D} for {DEMO} and required extrapolations beyond {ITER}}, language = {en}, - urldate = {2019-11-07}, - journal = {Journal of Nuclear Materials}, - author = {Wan, ChuBin and Yu, SuYe and Ju, Xin and Wang, WenWen}, - month = sep, - year = {2018}, - keywords = {Density Functional Theory}, - pages = {249--256}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CY6G5U3P\\S0022311518300060.html:text/html;Wan et al. - 2018 - Hydrogen trapping in helium-implanted W and W-Ta a.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NQQA4KE3\\Wan et al. - 2018 - Hydrogen trapping in helium-implanted W and W-Ta a.pdf:application/pdf}, + author = {Day, Christian}, + month = nov, + year = {2016}, + file = {Day - Tritium fuel cycle and self-sufficiency - R&D for .pdf:D\:\\Logiciels\\data_zotero\\storage\\FMLU5FXJ\\Day - Tritium fuel cycle and self-sufficiency - R&D for .pdf:application/pdf}, } -@article{yang_effect_2018, - title = {Effect of interatomic potential on the energetics of hydrogen and helium-vacancy complexes in bulk, or near surfaces of tungsten}, - volume = {512}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311518310766}, - doi = {10.1016/j.jnucmat.2018.10.032}, - abstract = {Hydrogen (H) trapping by helium-vacancy (HeV) complexes in bulk and the near surface region of tungsten (W) have been investigated by molecular statics calculations that evaluate two different WH interatomic potentials, which use the same WHe, HeHe and HeH potentials. One of the WH potentials is a bond-order potential (BOP) developed by Juslin et al., while the other is an embedding atom method (EAM) potential developed by Wang et al.. Both potentials overestimate the H binding energies to He clusters in bulk W, as compared to DFT calculations, but properly predict the functional form of the H binding energies to He clusters with increasing number of He and H. The BOP simulations reveal that H binding energies to HexV complexes generally increase with increasing number of He. However, the EAM results indicate that the H binding energy as a function of number of He depends on the number of H, and the H binding energies change slightly at high He content. Compared with available DFT data, both BOP and EAM underestimate the H binding energies to HexV2Hm complexes. The BOP reproduces the He formation energy below a W surface, while the EAM potential better reproduces the H formation energy and the interactions between H and HeV complexes. Based on these comparisons, we determine that the EAM potential is more accurate than BOP for large-scale molecular dynamics simulations of WHeH interactions. The EAM potential predicts that the difference in the average binding energies of H to stable HeV complexes near the W surface is less than 0.2 eV and the difference decreases with increasing He content. Thus, the EAM potential indicates that the effect of surfaces on H binding energies to large HeV complexes below the W surfaces can be ignored.}, +@article{abdou_blanketfirst_2015, + title = {Blanket/first wall challenges and required {R}\&{D} on the pathway to {DEMO}}, + volume = {100}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379615302465}, + doi = {10.1016/j.fusengdes.2015.07.021}, + abstract = {The breeding blanket with integrated first wall (FW) is the key nuclear component for power extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER device will address plasma burn physics and plasma support technology, but it does not have a breeding blanket. Current activities to develop “roadmaps” for realizing fusion power recognize the blanket/FW as one of the principal remaining challenges. Therefore, a central element of the current planning activities is focused on the question: what are the research and major facilities required to develop the blanket/FW to a level which enables the design, construction and successful operation of a fusion DEMO? The principal challenges in the development of the blanket/FW are: (1) the Fusion Nuclear Environment – a multiple-field environment (neutrons, heat/particle fluxes, magnetic field, etc.) with high magnitudes and steep gradients and transients; (2) Nuclear Heating in a large volume with sharp gradients – the nuclear heating drives most blanket phenomena, but accurate simulation of this nuclear heating can be done only in a DT-plasma based facility; and (3) Complex Configuration with blanket/first wall/divertor inside the vacuum vessel – the consequence is low fault tolerance and long repair/replacement time. These blanket/FW development challenges result in critical consequences: (a) non-fusion facilities (laboratory experiments) need to be substantial to simulate multiple fields/multiple effects and must be accompanied by extensive modeling; (b) results from non-fusion facilities will be limited and will not fully resolve key technical issues. A DT-plasma based fusion nuclear science facility (FNSF) is required to perform “multiple effects” and “integrated” experiments in the fusion nuclear environment; and (c) the Reliability/Availability/Maintainability/Inspectability (RAMI) of fusion nuclear components is a major challenge and is one of the primary reasons why the blanket/FW will pace fusion development toward a DEMO. This paper summarizes the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identifies the key R\&D needs in non-fusion and fusion facilities on the path to DEMO.}, language = {en}, - urldate = {2019-11-07}, - journal = {Journal of Nuclear Materials}, - author = {Yang, L. and Bergstrom, Z. J. and Wirth, B. D.}, - month = dec, - year = {2018}, - keywords = {Density Functional Theory}, - pages = {357--370}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\F9A8952E\\Yang et al. - 2018 - Effect of interatomic potential on the energetics .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\22YCX396\\S0022311518310766.html:text/html}, + urldate = {2021-12-27}, + journal = {Fusion Engineering and Design}, + author = {Abdou, Mohamed and Morley, Neil B. and Smolentsev, Sergey and Ying, Alice and Malang, Siegfried and Rowcliffe, Arthur and Ulrickson, Mike}, + month = nov, + year = {2015}, + keywords = {Blanket, Ceramic breeders, DCLL, First wall, Fusion nuclear science facility, Fusion nuclear technology, Fusion technology, Heat transfer, Liquid metals, Mass transfer, Materials, MHD, Tritium self-sufficiency}, + pages = {2--43}, } -@article{rieth_behavior_2019, - title = {Behavior of tungsten under irradiation and plasma interaction}, - volume = {519}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S002231151930025X}, - doi = {10.1016/j.jnucmat.2019.03.035}, +@article{busigin_dynamic_1992, + title = {Dynamic {Simulation} of the {ITER} {Fuel} {Cycle}}, + volume = {21}, + issn = {0748-1896}, + url = {https://www.tandfonline.com/doi/full/10.13182/FST92-A29867}, + doi = {10.13182/FST92-A29867}, + abstract = {А dynamic simulation has been developed for the ITER fuel cycle including vacuum pumpi11g, fuel processing, fueling, pellet injection, tritium breeding Ьlanket detritiation, fuel purification and isotope separation. The dynamic simulatio11 model is used for calculating the unsteady-state flow of materials throug{\textbackslash}1 tl1e various fuel processing systems. Since many of the systems have substantial hold-up times, and the ITER l"eactor burn and dwell cycle is periodic, а steady state model cannot provide а complete picture of system behavior. The dynamic model allows assessment of flowrates and minimum and maximum inveнtories under а wide range of dynamic conditions. This info1·mation is necessary for proper specification of system design requirements.}, language = {en}, - urldate = {2019-11-07}, - journal = {Journal of Nuclear Materials}, - author = {Rieth, Michael and Doerner, Russell and Hasegawa, Akira and Ueda, Yoshio and Wirtz, Marius}, - month = jun, - year = {2019}, - pages = {334--368}, - file = {Rieth et al. - 2019 - Behavior of tungsten under irradiation and plasma .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KRUH66F5\\Rieth et al. - 2019 - Behavior of tungsten under irradiation and plasma .pdf:application/pdf}, + number = {2P2}, + urldate = {2021-12-27}, + journal = {Fusion Technology}, + author = {Busigin, A. and Sood, S.K. and Kveton, O.K.}, + month = mar, + year = {1992}, + pages = {915--920}, + file = {Busigin et al. - 1992 - Dynamic Simulation of the ITER Fuel Cycle.pdf:D\:\\Logiciels\\data_zotero\\storage\\JRG2F4R4\\Busigin et al. - 1992 - Dynamic Simulation of the ITER Fuel Cycle.pdf:application/pdf}, } -@article{panizo-laiz_experimental_2019, - title = {Experimental and computational studies of the influence of grain boundaries and temperature on the radiation-induced damage and hydrogen behavior in tungsten}, - volume = {59}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab26e9}, - doi = {10.1088/1741-4326/ab26e9}, - abstract = {We study the influence of grain boundaries (GBs) on radiation-induced vacancies, as well as on the hydrogen (H) behavior in tungsten (W) samples with different grain sizes in the temperature range from 300 K to 573 K, both experimentally and by computer simulations. For this purpose, coarse-grained and nanostructured W samples were sequentially irradiated with carbon (C) and H ions at energies of 665 keV and 170 keV, respectively. A first set of the implanted samples was annealed at 473 K and a second set at 573 K. Object kinetic Monte Carlo simulations were performed to account for experimental outcomes. Results show that the number of vacancies for nanostructured W is always larger than for monocrystalline W samples in the whole studied temperature range and that the number of vacancies is only reduced in samples with a large density of grain boundaries and at temperatures high enough to activate the vacancy motion (around 573 K). Results also indicate that the migration of H along vacancy free grain boundaries is more effective than along the bulk, and that the retained H is trapped in vacancies located within the grains. These results are used to explain the experimental outcomes.}, +@article{glugla_tritium_2001, + title = {The tritium fuel cycle of {ITER}-{FEAT}}, + volume = {58-59}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379601003568}, + doi = {10.1016/S0920-3796(01)00356-8}, + abstract = {The Tritium Plant of ITER-FEAT is essential for the operation of the machine after the initial hydrogen phase, as tritium will be produced from DD fusion reactions. Within the fuel cycle of the Tokamak deuterium and later also tritium will be provided to the Fuelling Systems, and the unburned DT fraction recovered from the exhaust gases. The design of the tritium fuel cycle has to be based upon well proven technology to assure the safe handling of tritium along with credible accountancy, low tritium inventory, low generation of wastes and a high reliability of all components throughout the lifetime of ITER-FEAT.}, language = {en}, - number = {8}, - urldate = {2019-11-05}, - journal = {Nuclear Fusion}, - author = {Panizo-Laiz, M. and Díaz-Rodríguez, P. and Rivera, A. and Valles, G. and Martín-Bragado, I. and Perlado, J. M. and Munnik, F. and González-Arrabal, R.}, - month = jul, - year = {2019}, - keywords = {Monte Carlo}, - pages = {086055}, - file = {Panizo-Laiz et al. - 2019 - Experimental and computational studies of the infl.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SYIEQ89A\\Panizo-Laiz et al. - 2019 - Experimental and computational studies of the infl.pdf:application/pdf}, -} - -@article{becquart_migration_2006, - title = {Migration {Energy} of {He} in {W} {Revisited} by {Ab} {Initio} {Calculations}}, - volume = {97}, - url = {https://link.aps.org/doi/10.1103/PhysRevLett.97.196402}, - doi = {10.1103/PhysRevLett.97.196402}, - abstract = {We use state of the art ab initio calculations to obtain the diffusion properties of He in tungsten. The calculated migration energy of He is very low, around 0.06 eV. This value is much lower than the experimental field-ion microscopy results which lead to a migration energy of the order of 0.24—0.32 eV. The reason for this discrepancy is the high propensity for He to form He-He clusters characterized by a very large binding energy of the order of 1 eV. Such a large binding energy indicates that He atoms can be trapped by other He atoms and can explain the formation of He blisters close to the surface of He implanted tungsten.}, - number = {19}, - urldate = {2019-10-30}, - journal = {Physical Review Letters}, - author = {Becquart, Charlotte S. and Domain, Christophe}, + urldate = {2021-12-27}, + journal = {Fusion Engineering and Design}, + author = {Glugla, M and Busigin, A and Dörr, L and Haange, R and Hayashi, T and Kveton, O and Lässer, R and Murdoch, D. K and Nishi, M and Penzhorn, R. -D and Yoshida, H}, month = nov, - year = {2006}, - keywords = {Density Functional Theory}, - pages = {196402}, - file = {Becquart et Domain - 2006 - Migration Energy of He in W Revisited by Ab Initio.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IYHTPYVG\\Becquart et Domain - 2006 - Migration Energy of He in W Revisited by Ab Initio.pdf:application/pdf}, + year = {2001}, + keywords = {DD fusion, ITER-FEAT, Tritium fuel cycle, Tritium plant}, + pages = {349--353}, } -@article{takayama_first_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {First principles investigation of cluster consisting of hydrogen–helium atoms interstitially-trapped in tungsten}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S002231151400782X}, - doi = {10.1016/j.jnucmat.2014.11.001}, - abstract = {We evaluate the binding energies of mixed helium and hydrogen clusters consisted of interstitially trapped atoms in bcc tungsten by first-principles calculations based on density functional theories. It is shown that helium-rich interstitially-trapped clusters have the positive binding energies and the low electron-density region expand as the number of helium in the cluster increase. Thus, the helium-rich interstitially trapped clusters can act as a trapping site for hydrogen, and interstitially trapped helium interrupts or disturbs the hydrogen diffusion in tungsten.}, +@article{cristescu_iter_2005, + title = {{ITER} {Dynamic} {Tritium} {Inventory} {Modeling} {Code}}, + volume = {48}, + issn = {1536-1055, 1943-7641}, + url = {https://www.tandfonline.com/doi/full/10.13182/FST05-A939}, + doi = {10.13182/FST05-A939}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Takayama, A. and Ito, A. M. and Oda, Y. and Nakamura, H.}, + number = {1}, + urldate = {2021-12-27}, + journal = {Fusion Science and Technology}, + author = {Cristescu, Ioana-R. and Dörr, L. and Busigin, A. and Murdoch, D.}, month = aug, - year = {2015}, - keywords = {Density Functional Theory}, - pages = {355--358}, - file = {Takayama et al. - 2015 - First principles investigation of cluster consisti.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XDGGDE55\\Takayama et al. - 2015 - First principles investigation of cluster consisti.pdf:application/pdf}, + year = {2005}, + pages = {343--348}, + file = {Cristescu et al. - 2005 - ITER Dynamic Tritium Inventory Modeling Code.pdf:D\:\\Logiciels\\data_zotero\\storage\\QK63IACZ\\Cristescu et al. - 2005 - ITER Dynamic Tritium Inventory Modeling Code.pdf:application/pdf}, } -@article{hodille_hydrogen_2018, - title = {Hydrogen supersaturated layers in {H}/{D} plasma-loaded tungsten: {A} global model based on thermodynamics, kinetics and density functional theory data}, - volume = {2}, - shorttitle = {Hydrogen supersaturated layers in {H}/{D} plasma-loaded tungsten}, - url = {https://link.aps.org/doi/10.1103/PhysRevMaterials.2.093802}, - doi = {10.1103/PhysRevMaterials.2.093802}, - abstract = {In this paper, we combine density functional theory data with a thermodynamic and a kinetic model to determine the total concentration of hydrogen implanted in the subsurface of tungsten exposed to a hydrogen flux. The subsurface hydrogen concentration is calculated given a flux of hydrogen, a temperature of implantation, and the energy of the incoming hydrogen ions as independent variables. This global model is built step by step; an equilibrium between atomic hydrogen within bulk tungsten and a molecular hydrogen gas phase is first considered, and the calculated solubility is compared with experimental results. Subsequently, a kinetic model is used to determine the chemical potential for hydrogen in the subsurface of tungsten. Combining both these models, two regimes are established in which hydrogen is preferentially trapped either at interstitial sites or in vacancies. We deduce from our model that the existence of these two regimes is driven by the temperature of the implanted tungsten sample; above a threshold or transition temperature is the interstitial regime, and below is the vacancy regime in which supersaturated layers form within tenths of an angstrom below the surface. A simple analytical expression is derived for the coexistence of the two regimes depending on the implantation temperature, the incident energy, and the flux of the hydrogen ions which we use to plot the corresponding phase diagram.}, - number = {9}, - urldate = {2019-10-07}, - journal = {Physical Review Materials}, - author = {Hodille, E. A. and Fernandez, N. and Piazza, Z. A. and Ajmalghan, M. and Ferro, Y.}, - month = sep, +@article{you_european_2018, + title = {European divertor target concepts for {DEMO}: {Design} rationales and high heat flux performance}, + volume = {16}, + issn = {2352-1791}, + shorttitle = {European divertor target concepts for {DEMO}}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179118300437}, + doi = {10.1016/j.nme.2018.05.012}, + abstract = {The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating. For reliable exhaust of huge thermal power, robust and durable divertor target PFCs with a sufficiently large heat removal capability and lifetime has to be developed. Since 2014 in the framework of the preconceptual design activities of the EUROfusion DEMO project, integrated R\&D efforts have been made in the subproject ‘Target development’ of the work package ‘Divertor’ to develop divertor target PFCs for DEMO. Recently, the first R\&D phase was concluded where six (partly novel) target PFC concepts were developed and evaluated by means of non-destructive inspections and high-heat-flux fatigue testing. In this paper, the major achievements of the first phase activities in this subproject are presented focusing on the design rationales of the target PFC concepts, technology options employed for small-scale mock-up fabrication and the results of the first round high-heat-flux qualification test campaign. It is reported that the mock-ups of three PFC concepts survived up to 500 loading cycles at 20 MW/m² (with hot water cooling at 130 °C) without any discernable indication of degradation in performance or structural integrity.}, + language = {en}, + urldate = {2021-12-22}, + journal = {Nuclear Materials and Energy}, + author = {You, J. H. and Visca, E. and Barrett, T. and Böswirth, B. and Crescenzi, F. and Domptail, F. and Fursdon, M. and Gallay, F. and Ghidersa, B-E. and Greuner, H. and Li, M. and Müller, A. v. and Reiser, J. and Richou, M. and Roccella, S. and Vorpahl, Ch.}, + month = aug, year = {2018}, - keywords = {Density Functional Theory}, - pages = {093802}, + keywords = {DEMO, Composites, Divertor targets, EUROfusion, High-heat-flux, Plasma-facing component}, + pages = {1--11}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2MSX7RJF\\You et al. - 2018 - European divertor target concepts for DEMO Design.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MDAWITGD\\S2352179118300437.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\IIX5LQ7G\\You et al. - 2018 - European divertor target concepts for DEMO Design.pdf:application/pdf}, } -@article{kato_super-saturated_2015, - title = {Super-saturated hydrogen effects on radiation damages in tungsten under the high-flux divertor plasma irradiation}, - volume = {55}, - issn = {0029-5515}, - doi = {10.1088/0029-5515/55/8/083019}, - abstract = {Tungsten is a prime candidate as the divertor material of the ITER and DEMO reactors, which would be exposed to unprecedentedly high-flux plasmas as well as neutrons. For a better characterization of radiation damages in the tungsten under the divertor condition, we examine influences of super-saturated hydrogen on vacancies in the tungsten. The present calculations based on density functional theory (DFT) reveal unusual phenomena predicted at a super-saturated hydrogen concentration: (1) strongly enhanced vacancy concentration with the super-saturated hydrogen concentration is predicted by a thermodynamics model assuming multiple-hydrogen trapping, i.e. hydrogen clusters formation, in the vacancies; and (2) DFT molecular dynamics revealed that hydrogen clusters can prevent a vacancy from recombining with the neighboring crowdion-type self-interstitial-atom. This suggests that neutron damage effects will be increased in the presence of the hydrogen clusters.}, +@article{domptail_design_2020, + title = {The design and optimisation of a monoblock divertor target for {DEMO} using thermal break interlayer}, + volume = {154}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379620300454}, + doi = {10.1016/j.fusengdes.2020.111497}, + abstract = {A high performing DEMO divertor target mock-up design that uses the thermal break interlayer concept is presented. The design evolved from a previous design of which six mock-ups were designed, fabricated and subjected to high heat flux testing. The new design was generated using optimisation techniques; specifically, software was developed to automatically process the design of experiments data to enable visualisation of the design space. Despite the more challenging geometric constraints of this second phase, this design performs significantly better than that of the previous phase; the strain in the interlayer, which was the dominant damage mode in the phase 1 testing, is reduced by 28\%. Four mock-ups of the selected design were manufactured, all of which successfully passed a series of high heat flux testing, including 500 cycles at 20 MW/m2. Design optimisation methods are not widely utilised in fusion engineering, their potential benefits, which are demonstrated here on a plasma facing component, could be applied to many other challenging designs.}, language = {en}, - number = {8}, - urldate = {2019-10-07}, - journal = {Nuclear Fusion}, - author = {Kato, D. and Iwakiri, H. and Watanabe, Y. and Morishita, K. and Muroga, T.}, - month = jul, - year = {2015}, - keywords = {Density Functional Theory}, - pages = {083019}, - file = {Kato et al. - 2015 - Super-saturated hydrogen effects on radiation dama.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UZTTL3RP\\Kato et al. - 2015 - Super-saturated hydrogen effects on radiation dama.pdf:application/pdf}, + urldate = {2021-12-22}, + journal = {Fusion Engineering and Design}, + author = {Domptail, F. and Barrett, T. R. and Fursdon, M. and Lukenskas, A. and You, J-H.}, + month = may, + year = {2020}, + keywords = {DEMO, Design optimisation, Divertor target, High heat flux, Thermal break}, + pages = {111497}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9MP3TG8C\\S0920379620300454.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\6T3IFVCD\\Domptail et al. - 2020 - The design and optimisation of a monoblock diverto.pdf:application/pdf}, } -@article{begrambekov_hydrogen_2014, - title = {Hydrogen transport through oxide metal surface under atom and ion irradiation}, - volume = {567}, - issn = {1742-6596}, - doi = {10.1088/1742-6596/567/1/012003}, - abstract = {Both the latest and earlier achieved results on gas exchange processes on metal surfaces (including stainless steel, titanium, zirconium, tungsten with deposited aluminum oxide coating) under hydrogen atom or plasma irradiation with occasional oxygen impurity are presented in the paper. Mechanisms and regularities of these processes are discussed. It is demonstrated that surface oxide layer properties as a diffusion barrier strongly depend on external influence on the surface. In particular, it is revealed that low energy hydrogen ion irradiation could slow down hydrogen desorption from metals. Hydrogen atom or ion irradiation combined with simultaneous oxygen admixture accelerates hydrogen desorption from metals.}, +@article{gilardi_comparison_2021, + title = {Comparison of two modelling tools for the evaluation of tritium and hydrogen transfers in nuclear reactors or complex systems}, + volume = {166}, + issn = {09203796}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379621000545}, + doi = {10.1016/j.fusengdes.2021.112278}, + abstract = {In the framework of the TRANSAT project, started in 2017 (TRANSversal Actions for Tritium supported within the H2020 Euratom program), the ability to measure and to assess the tritium inventory and migration within different kinds of reactors or processes is one major challenge to control the potential releases and personal dosimetry in nominal operating conditions.}, language = {en}, - journal = {Journal of Physics: Conference Series}, - author = {Begrambekov, L. and Dvoychenkova, O. and Evsin, A. and Kaplevsky, A. and Sadovskiy, Ya and Schitov, N. and Vergasov, S. and Yurkov, D.}, - month = nov, - year = {2014}, - pages = {012003}, - file = {Begrambekov et al. - 2014 - Hydrogen transport through oxide metal surface und.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BP4893KY\\Begrambekov et al. - 2014 - Hydrogen transport through oxide metal surface und.pdf:application/pdf}, + urldate = {2021-12-17}, + journal = {Fusion Engineering and Design}, + author = {Gilardi, T. and Moreno, C. and Grisolia, C.}, + month = may, + year = {2021}, + pages = {112278}, + file = {Gilardi et al. - 2021 - Comparison of two modelling tools for the evaluati.pdf:D\:\\Logiciels\\data_zotero\\storage\\DWJEZMR7\\Gilardi et al. - 2021 - Comparison of two modelling tools for the evaluati.pdf:application/pdf}, } -@article{wirth_challenges_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Challenges and opportunities of modeling plasma–surface interactions in tungsten using high-performance computing}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514008757}, - doi = {10.1016/j.jnucmat.2014.11.072}, - abstract = {The performance of plasma facing components (PFCs) is critical for ITER and future magnetic fusion reactors. The ITER divertor will be tungsten, which is the primary candidate material for future reactors. Recent experiments involving tungsten exposure to low-energy helium plasmas reveal significant surface modification, including the growth of nanometer-scale tendrils of “fuzz” and formation of nanometer-sized bubbles in the near-surface region. The large span of spatial and temporal scales governing plasma surface interactions are among the challenges to modeling divertor performance. Fortunately, recent innovations in computational modeling, increasingly powerful high-performance computers, and improved experimental characterization tools provide a path toward self-consistent, experimentally validated models of PFC and divertor performance. Recent advances in understanding tungsten–helium interactions are reviewed, including such processes as helium clustering, which serve as nuclei for gas bubbles; and trap mutation, dislocation loop punching and bubble bursting; which together initiate surface morphological modification.}, +@article{franza_tritium_2013, + title = {Tritium transport analysis in {HCPB} {DEMO} blanket with the {FUS}-{TPC} code}, + volume = {88}, + issn = {09203796}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379613004857}, + doi = {10.1016/j.fusengdes.2013.05.045}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Wirth, Brian D. and Hammond, K. D. and Krasheninnikov, S. I. and Maroudas, D.}, - month = aug, - year = {2015}, - pages = {30--38}, - file = {Wirth et al. - 2015 - Challenges and opportunities of modeling plasma–su.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BESUFI9U\\Wirth et al. - 2015 - Challenges and opportunities of modeling plasma–su.pdf:application/pdf}, + number = {9-10}, + urldate = {2021-12-17}, + journal = {Fusion Engineering and Design}, + author = {Franza, F. and Boccaccini, L.V. and Ciampichetti, A. and Zucchetti, M.}, + month = oct, + year = {2013}, + pages = {2444--2447}, + file = {Franza et al. - 2013 - Tritium transport analysis in HCPB DEMO blanket wi.pdf:D\:\\Logiciels\\data_zotero\\storage\\9CV3CLHU\\Franza et al. - 2013 - Tritium transport analysis in HCPB DEMO blanket wi.pdf:application/pdf}, } -@article{pezzoli_thermal_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Thermal annealing and exposure to divertor-like deuterium plasma of tailored tungsten oxide coatings}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514008265}, - doi = {10.1016/j.jnucmat.2014.11.035}, - abstract = {In this work we produced tungsten (W) and W oxide (WOx) films by pulsed laser deposition (PLD) with the aim of the addressing modifications of structure and morphology that occur after annealing treatments and high-flux deuterium plasma. Thanks to the high flexibility of PLD we produced nanostructured W containing non-bounded oxygen, different types of WOx and multilayered films. W coatings are dense, non-porous and exhibit a nanocrystalline structure, resembling the coatings used as first wall in tokamaks. The oxide films are nearly stoichiometric amorphous WOx (x=3) with different morphology from compact to porous. Depending on annealing temperature, nucleation of different crystalline phases (e.g. WO3, W18O49) occurs. Exposure of films to high-flux (∼1024m−2s−1) deuterium plasmas in Magnum-PSI at different surface temperatures (Tmax=580K) determines material modifications at the nanoscale (e.g. nanometric defects) but no delamination. In addition preliminary deuterium retention results are reported.}, +@techreport{chang_h_oh_development_2009, + title = {Development and {Verification} of {Tritium} {Analyses} {Code} for a {Very} {High} {Temperature} {Reactor}}, + url = {http://www.osti.gov/servlets/purl/969495-ytycuv/}, language = {en}, - urldate = {2019-10-25}, - journal = {Journal of Nuclear Materials}, - author = {Pezzoli, A. and Dellasega, D. and Russo, V. and Gallo, A. and Zeijlmans van Emmichoven, P. A. and Passoni, M.}, - month = aug, - year = {2015}, - pages = {1041--1044}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\46RUDJNV\\Pezzoli et al. - 2015 - Thermal annealing and exposure to divertor-like de.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4TUHYL4L\\S0022311514008265.html:text/html}, + number = {INL/EXT-09-16743, 969495}, + urldate = {2021-12-17}, + author = {{Chang H. Oh} and {Eung S. Kim}}, + month = sep, + year = {2009}, + doi = {10.2172/969495}, + pages = {INL/EXT--09--16743, 969495}, + file = {Chang H. Oh et Eung S. Kim - 2009 - Development and Verification of Tritium Analyses C.pdf:D\:\\Logiciels\\data_zotero\\storage\\NK8GYRN2\\Chang H. Oh et Eung S. Kim - 2009 - Development and Verification of Tritium Analyses C.pdf:application/pdf}, } -@article{longhurst_soret_1985, - title = {The soret effect and its implications for fusion reactors}, - volume = {131}, +@misc{kohn-seemann_alfkoehnfusion_plots_2021, + title = {alfkoehn/fusion\_plots: {Second} release of the fusion plot package (new plots added)}, + shorttitle = {alfkoehn/fusion\_plots}, + url = {https://zenodo.org/record/4946068}, + abstract = {The following plots have been added to the second release binding\_energy CMA\_diagram fusion\_cross\_section fusion\_reactivity plasma\_zoo}, + urldate = {2021-08-19}, + publisher = {Zenodo}, + author = {Köhn-Seemann, Alf and Hillairet, Julien}, + month = jun, + year = {2021}, + doi = {10.5281/zenodo.4946068}, + file = {Zenodo Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5H5FMU8A\\4946068.html:text/html;Zenodo Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2TNUBVHR\\4946068.html:text/html}, +} + +@article{thompson_identifying_2021, + title = {Identifying microstructural changes responsible for retarded grain growth during tungsten recrystallization after helium plasma exposure}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/0022311585904258}, - doi = {10.1016/0022-3115(85)90425-8}, - abstract = {Tritium permeation through and retention in fusion reactor structures may be strongly influenced by the heat load carried by the structures through the Soret effect. After a short discussion suggestive of a heuristic model for predicting the associated energy and the heat of transport, data from several experiments are analyzed to show that the simplistic model works reasonably well with endothermic materials such as Fe and Ni, but is less successful with hydride formers. The implications of the model for tritium permeation and retention are discussed, and sample calculations are presented to illustrate the importance of properly accounting for the Soret effect in predicting tritium permeation and retention in fusion reactor structures. Neglecting the Soret effect may result in order of magnitude errors in estimating permeation and retention, while accounting for temperature sensitivity in the heat of transport will result in less significant corrections. An Appendix summarizes the development of transport equations from non-equilibrium thermodynamics to clarify the relationships between the various transport parameters involved.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311521006681}, + doi = {10.1016/j.jnucmat.2021.153448}, + abstract = {Helium plasma is known to affect recrystallization in tungsten, with lower temperatures during plasma exposure leading to slower crystal grain growth. To understand why this occurs, tungsten samples were first exposed to helium plasma at surface temperatures between 300°C and 800°C, before annealing at temperatures between 1100°C and 1400°C. Annealing after helium exposure at 300°C was confirmed to lead to smaller crystal grains than annealing after exposure to helium at 500°C. Small 1-2 nm radius nanobubbles formed readily in tungsten after helium plasma exposure, but disappear after annealing at temperatures of 1100°C and above. The formation of cracks and open volumes beneath the surface was observed exclusively in tungsten exposed to helium-plasma at 300°C, with extensive surface cracks visible after annealing. These cracks were not observed for higher temperature helium exposure and likely form due to the strong tendency of bubbles to cluster along grain boundaries for helium exposure at 300°C. Despite this, nano-mechanical testing revealed a similar influence of annealing conditions on tungsten hardness for all plasma exposure conditions studied. The crack formation is likely caused by interactions between solute helium and residual defects from surface polishing.}, language = {en}, - number = {1}, - urldate = {2019-10-25}, + urldate = {2021-12-12}, journal = {Journal of Nuclear Materials}, - author = {Longhurst, Glen R.}, - month = mar, - year = {1985}, - pages = {61--69}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\86GHHQVC\\Longhurst - 1985 - The soret effect and its implications for fusion r.pdf:application/pdf}, + author = {Thompson, M. A. T. and Song, K. and De Temmerman, G. and Chen, H. and Kirby, N. and Bradby, J. and Bhattacharyya, D. and Hoang, Calvin and Corr, C. S.}, + month = dec, + year = {2021}, + pages = {153448}, } -@article{alimov_surface_2011, - title = {Surface morphology and deuterium retention in tungsten oxide layers exposed to low-energy, high flux {D} plasma}, - volume = {409}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311510008500}, - doi = {10.1016/j.jnucmat.2010.12.028}, - abstract = {Surface morphology and deuterium retention in tungsten oxide layers (WO3−z, z⩽0.25) grown on polycrystalline and recrystallized W substrates have been examined after exposure to a low-energy (38eV/D), high flux (1022D/m2s) D plasma to an ion fluence of 1026D/m2 at various temperatures (up to ∼700K). Characterization methods used were scanning electron microscopy, X-ray diffraction, Rutherford backscattering spectroscopy, and the D(3He,p)4He nuclear reaction analysis. During exposure to the D plasma at temperatures of 340–615K, a partial reduction of the tungsten oxide takes place in the near-surface layer up to 0.3μm in depth. Even at around room temperature, deuterium atoms diffuse several micrometers into the tungsten oxide. The high D concentration of about 0.1D/W observed in the first micrometers below the surface at temperatures below 500K can be related mainly to D atoms chemically bonded to O atoms. As the exposure temperature increases, the D concentration decreases, reaching about 2×10−4D/W at 615K. At plasma exposure temperatures of about 700K, the oxide layer shrinks and loses a large fraction of oxygen.}, - number = {1}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Alimov, V. K. and Tyburska, B. and Balden, M. and Lindig, S. and Roth, J. and Isobe, K. and Yamanishi, T.}, - month = feb, - year = {2011}, - pages = {27--32}, - file = {Alimov et al. - 2011 - Surface morphology and deuterium retention in tung.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\V8JAGRHW\\Alimov et al. - 2011 - Surface morphology and deuterium retention in tung.pdf:application/pdf}, +@article{dhard_plasma-wall_2021, + title = {Plasma-wall interaction studies in {W7}-{X}: main results from the recent divertor operations}, + volume = {96}, + issn = {1402-4896}, + shorttitle = {Plasma-wall interaction studies in {W7}-{X}}, + url = {https://doi.org/10.1088/1402-4896/ac35c0}, + doi = {10.1088/1402-4896/ac35c0}, + abstract = {Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D geometry of W7-X were carried out by in situ spectroscopic observations, exhaust gas analysis and post-mortem measurements on a large number of plasma-facing components extracted after campaigns. The investigations showed that the divertor strike line areas on the divertor targets appeared to be the major source of carbon impurities. After multistep erosion and deposition events, carbon was found to be deposited largely at the first wall components, with thick deposits of {\textgreater}1 μm on some baffle tiles, moderate deposits on toroidal closure tiles and thin deposits at the heat shield tiles and the outer wall panels. Some amount of the eroded carbon was pumped out via the vacuum pumps as volatile hydrocarbons and carbon oxides (CO, CO2) formed due to the chemical processes. Boron was introduced by three boronizations and one boron powder injection experiment. Thin boron-dominated layers were found on the inner heat shield and the outer wall panels, some boron was also found at the test divertor unit and in redeposited layers together with carbon. Local erosion/deposition and global migration processes were studied using field-line transport simulations, analytical estimations, 3D-WallDYN and ERO2.0 modeling in standard magnetic field configuration.}, + language = {en}, + number = {12}, + urldate = {2021-12-09}, + journal = {Physica Scripta}, + author = {Dhard, C. P. and Brezinsek, S. and Mayer, M. and Naujoks, D. and Masuzaki, S. and Zhao, D. and Yi, R. and Oelmann, J. and Schmid, K. and Romazanov, J. and Pardanaud, C. and Kandler, M. and Kharwandikar, A. K. and Schlisio, G. and Volzke, O. and Grote, H. and Gao, Y. and Rudischhauser, L. and Goriaev, A. and Wauters, T. and Kirschner, A. and Sereda, S. and Wang, E. and Rasinski, M. and Dittmar, T. and Motojima, G. and Hwangbo, D. and Kajita, S. and Balden, M. and Burwitz, V. V. and Neu, R. and Linsmeier, Ch and Team, the W7-X.}, + month = nov, + year = {2021}, + note = {Publisher: IOP Publishing}, + pages = {124059}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SM7M5FVJ\\Dhard et al. - 2021 - Plasma-wall interaction studies in W7-X main resu.pdf:application/pdf}, } -@article{inouye_hydrogen_2009, - series = {Proceedings of the 16th {International} {Conference} on {Ion} {Beam} {Modification} of {Materials}}, - title = {Hydrogen retention induced by ion implantation in tungsten trioxide films}, - volume = {267}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X09001165}, - doi = {10.1016/j.nimb.2009.01.139}, - abstract = {The relation between hydrogen retention and optical properties of an amorphous tungsten trioxide (WO3) film was investigated using 10keV H2+ ion implantation. WO3 films (350nm) covered by W layers (200nm) were deposited on SiO2 glass substrates by sputtering in a mixture of Ar and O2 gases. The hydrogen concentration in the WO3 film was characterized by elastic recoil detection analysis (ERDA). The hydrogen concentration in the WO3 film increased by 0.4 H/W in proportion to the fluence of the H2+ ions implanted into the W layer. The optical absorption coefficient of the film at 750nm increased linearly by 3μm−1 with an increase in the concentration of the implanted hydrogen up to 0.1 H/W, and saturated at 4μm−1 with the concentration higher than 0.1 H/W. These results indicate that the introduced hydrogen up to a hydrogen concentration of 0.1 H/W can be monitored by measuring the optical absorbance in the WO3 films.}, - number = {8}, - urldate = {2019-10-07}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Inouye, Aichi and Yamamoto, Shunya and Nagata, Shinji and Yoshikawa, Masahito and Shikama, Tatsuo}, - month = may, - year = {2009}, - pages = {1480--1483}, - file = {Inouye et al. - 2009 - Hydrogen retention induced by ion implantation in .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\E88X9A75\\Inouye et al. - 2009 - Hydrogen retention induced by ion implantation in .pdf:application/pdf}, +@article{hodille_modelling_2021, + title = {Modelling of hydrogen isotopes trapping, diffusion and permeation in divertor monoblocks under {ITER}-like conditions}, + copyright = {All rights reserved}, + issn = {0029-5515}, + url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac2abc}, + doi = {10.1088/1741-4326/ac2abc}, + abstract = {In this work, the deuterium (D) retention in plasma facing components of the divertor of ITER is estimated. Three scenarios are simulated with 3 different surface temperatures, 1456 K, 870 K and 435 K. They represent the exposure of different parts of the divertor during an attached plasma. Our 1D rate equation model MHIMS (migration of hydrogen isotopes in materials) is used to model the retention in the super-saturated layer formed in the first 10 nm: the D retention integrated in this 10-nm layer is 1e19 Dm-2 for the coldest scenarios. It is also used to differentiate the evolution of deuterium retention during pulsed and continuous plasma exposure which shows that: (i) there is a retention during the ramp-down in the first 10 µm which is released during the ramp-up and (ii) the bulk retention is not affected by the cycling of plasma exposure. The concentration of mobile deuterium in the implantation zone is used as an input of our finite element code FESTIM which is used to assess the deuterium retention and migration in the 2D complex geometry of the actively cooled plasma facing components. In the end, this work enable to determine the three following macroscopic quantities: the total deuterium retention, the permeation flux to the cooling pipe and the desorption flux from the toroidal edges of the components. It is shown that (i) the coldest scenario leads to the highest retention despite the lowest exposure flux which has already been observed in past retention studies, (ii) the permeation to the cooling pipes happens after few thousands of seconds only for the hottest scenario, (iii) the release of deuterium from the toroidal edges is a small fuel recycling source.}, + language = {en}, + urldate = {2021-10-04}, + journal = {Nuclear Fusion}, + author = {Hodille, Etienne Augustin and Delaporte-Mathurin, Rémi and Denis, Julien and Pečovnik, Matic and Bernard, Elodie and Ferro, Yves and Sakamoto, Ryuichi and Charles, Yann and Mougenot, Jonathan and De Backer, Andree and Becquart, Charlotte S and Markelj, Sabina and Grisolia, Christian}, + year = {2021}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\RG7VVKUX\\Hodille et al. - 2021 - Modelling of hydrogen isotopes trapping, diffusion.pdf:application/pdf}, +} + +@article{delaporte-mathurin_influence_2021, + title = {Influence of exposure conditions on helium transport and bubble growth in tungsten}, + volume = {11}, + copyright = {2021 The Author(s)}, + issn = {2045-2322}, + url = {https://www.nature.com/articles/s41598-021-93542-9}, + doi = {10.1038/s41598-021-93542-9}, + abstract = {Helium diffusion, clustering and bubble nucleation and growth is modelled using the finite element method. The existing model from Faney et al. (Model Simul Mater Sci Eng 22:065010, 2018; Nucl Fusion 55:013014, 2015) is implemented with FEniCS and simplified in order to greatly reduce the number of equations. A parametric study is performed to investigate the influence of exposure conditions on helium inventory, bubbles density and size. Temperature is varied from 120 K to 1200 K and the implanted flux of 100 eV He is varied from \$\$10{\textasciicircum}\{17\}{\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$to \$\$5 {\textbackslash}times 10{\textasciicircum}\{21\}{\textbackslash}, \{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$. Bubble mean size increases as a power law of time whereas the bubble density reaches a maximum. The maximum He content in bubbles was approximately \$\$4 {\textbackslash}times 10{\textasciicircum}\{8\}\$\$He at \$\$5 {\textbackslash}times 10{\textasciicircum}\{21\}{\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$. After 1 h of exposure, the helium inventory varies from \$\$5 {\textbackslash}times 10{\textasciicircum}\{16\} {\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}\}\$\$at low flux and high temperature to \$\$10{\textasciicircum}\{25\} {\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}\}\$\$at high flux and low temperature. The bubbles inventory varies from \$\$5 {\textbackslash}times 10{\textasciicircum}\{12\}\$\$bubbles m\$\${\textasciicircum}\{-2\}\$\$to \$\$2 {\textbackslash}times 10{\textasciicircum}\{19\}\$\$bubbles m\$\${\textasciicircum}\{-2\}\$\$. Comparison with experimental measurements is performed. The bubble density simulated by the model is in quantitative agreement with experiments.}, + language = {en}, + number = {1}, + urldate = {2021-11-10}, + journal = {Scientific Reports}, + author = {Delaporte-Mathurin, Rémi and Ialovega, Mykola and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Bernard, Elodie and Martin, Céline and Grisolia, Christian}, + month = jul, + year = {2021}, + keywords = {Applied mathematics, Materials science, Mathematics and computing, Theory and computation}, + pages = {14681}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\BU5M53CW\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf;Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\C9JC5HZP\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf;Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2NCIHGZF\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QGSKDP59\\s41598-021-93542-9.html:text/html}, } -@article{nagata_hydrogen_2007, - series = {Proceedings of the {International} {Symposium} on {Metal}-{Hydrogen} {Systems}, {Fundamentals} and {Applications} ({MH2006})}, - title = {Hydrogen incorporation and gasochromic coloration of tungsten oxide films}, - volume = {446-447}, - issn = {0925-8388}, - url = {http://www.sciencedirect.com/science/article/pii/S0925838807000886}, - doi = {10.1016/j.jallcom.2007.01.039}, - abstract = {The retention and release of hydrogen were studied in connection with the gasochromic coloration and bleaching of tungsten oxide (WO3) thin films prepared by RF magnetron sputtering at various substrate temperatures. The concentration depth profiles of hydrogen in the WO3 film were measured by the Elastic Recoil Detection Analysis technique. The hydrogen was effectively incorporated and was uniformly distributed in the WO3 films deposited at the higher substrate temperatures above 400K, where crystalline structure was formed with a preferred orientation. Excellent gasochromic characteristics were found for the highly oriented crystalline WO3 film covered with a Pd layer. In situ measurements of hydrogen retention and optical transmission of the WO3 demonstrated that hydrogen concentration in the WO3 film increased with decreasing the optical transmission during the exposure of hydrogen gas.}, - urldate = {2019-10-07}, - journal = {Journal of Alloys and Compounds}, - author = {Nagata, S. and Inouye, A. and Yamamoto, S. and Tsuchiya, B. and Takano, K. and Toh, K. and Shikama, T.}, +@article{dark_influence_2021, + title = {Influence of hydrogen trapping on {WCLL} breeding blanket performances}, + volume = {61}, + copyright = {All rights reserved}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/ac28b0}, + doi = {10.1088/1741-4326/ac28b0}, + abstract = {Tritium transport simulations in water-cooled lithium lead (WCLL) breeding blankets have been performed with FESTIM. Fluid dynamics and heat transfer were coupled to evaluate how temperature and LiPb velocity fields affect tritium transport. The 2D WCLL model consisted of tungsten, EUROFER and liquid LiPb. Tritium inventories and permeation fluxes have been computed and the influence of trapping effects in solid domains was highlighted. It was evaluated that inclusion of trapping mechanisms increases inventory values by 15\% and delays permeation to the cooling channels. A parametric study was conducted to investigate the impact of the uncertainty in the literature (2 orders of magnitude) regarding hydrogen solubility in LiPb on these quantities. Varying the lithium lead solubility over the range found in the literature was found to vary the EUROFER inventory by a factor of 25. Permeation fluxes to the coolant channels was found to vary over a factor of 3.}, + language = {en}, + number = {11}, + urldate = {2021-12-08}, + journal = {Nuclear Fusion}, + author = {Dark, James and Delaporte-Mathurin, Remi and Charles, Yann and Hodille, Etienne A. and Grisolia, Christian and Mougenot, Jonathan}, month = oct, - year = {2007}, - pages = {558--561}, - file = {Nagata et al. - 2007 - Hydrogen incorporation and gasochromic coloration .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BK8BFPSE\\Nagata et al. - 2007 - Hydrogen incorporation and gasochromic coloration .pdf:application/pdf}, + year = {2021}, + note = {Publisher: IOP Publishing}, + pages = {116076}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ICCH6ZVV\\Dark et al. - 2021 - Influence of hydrogen trapping on WCLL breeding bl.pdf:application/pdf}, } -@article{heuer_aiming_2018, - title = {Aiming at understanding thermo-mechanical loads in the first wall of {DEMO}: {Stress}–strain evolution in a {Eurofer}-tungsten test component featuring a functionally graded interlayer}, - volume = {135}, - issn = {0920-3796}, - shorttitle = {Aiming at understanding thermo-mechanical loads in the first wall of {DEMO}}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618305660}, - doi = {10.1016/j.fusengdes.2018.07.011}, - abstract = {For the future fusion demonstration power plant, DEMO, several blanket designs are currently under consideration. Despite geometric and operational differences, all designs suggest a first wall (FW), in which tungsten (W) armour is joined to a structure made of Reduced Activation Ferritic Martensitic (RAFM) steel. In thermo-mechanical analyses of breeding blankets, this joint has received limited attention. In order to provide a basis for better understanding of thermally induced stresses and strains in the FW, the thermo-mechanical behaviour of a water-cooled test component is explored in the current contribution. The model aims at providing a simple geometry that allows straightforward comparison of numerical and experimental results, while trying to keep boundary conditions as realistic as possible. A test component with direct RAFM steel-W joint, and a test component with a stress-redistributing, functionally graded RAFM steel/W interlayer in the joint is considered in the current contribution. The analyses take production- and operation-related loads into account. Following a detailed analysis of the evolution of stress components and strain in the model, a parameter study with respect to geometric specifications and loads is presented. The analyses show that, even in a small test component, a direct RAFM steel-W joint causes enormous plastic deformation. The implementation of a functionally graded interlayer reduces stresses and strains significantly, but vertical normal stresses at the joint's circumference remain considerable. With the component geometry considered here, the graded interlayer should be at least 1 mm thick and contain 4 sublayers to appropriately redistribute stresses. Beyond a component width of 14 mm, stresses increase strongly, which may pose a risk to the applicability of large-scale FW components, too.}, +@article{lasa_integrated_2021, + title = {Integrated model predictions on the impact of substrate damage on gas dynamics during {ITER} burning-plasma operations}, + volume = {61}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/ac2875}, + doi = {10.1088/1741-4326/ac2875}, + abstract = {Divertor design and choice of plasma-facing materials (PFM) will be essential to the success of next-generation fusion reactors as they operate under more powerful scenarios. Understanding and controlling interactions between the plasma and PFM is essential to making these choices. Within these plasma–material interactions and especially in tungsten (W), the interplay between the most abundant plasma species (hydrogen isotopes and helium, He) with the wall material alters fuel retention. However, this interplay is yet to be sufficiently understood to confidently project fuel retention levels to future fusion devices. The paper presents a series of integrated simulations of fusion plasmas and their interaction with tungsten. Specifically, this study assesses the impact of He plasma pre-exposure on hydrogenic species retention during 100 s of burning plasma operations (BPO) in ITER. Multiple pre-exposure scenarios are considered, including sub-surface damage resulting from exposures in the linear device PISCES and from early ITER He-operation. The predictions from these consecutive He-BPO exposures show that fuel content and spatial distribution in the material are largely determined by the He-induced damage, as manifest in: (i) changes in surface temperature expected during BPO have little effect on fuel retention in the presence of He-induced damage; (ii) gas content stabilizes quickly in substrates pre-exposed in PISCES, at levels set by the concentration of pre-existing vacancies, while it continues to increase in substrates initially pristine or pre-exposed to ITER He plasmas; (iii) the presence of He and He–V clusters in the near-surface region locally increases hydrogenic retention, but decreases its permeation; this results in hydrogenic species that remain closer to the surface in pre-damaged substrates, while the bulk content is higher for initially pristine cases. In summary, the interaction and binding of D and T with the pre-existing He–V clusters modifies retention and permeation of hydrogen species during ITER BPO.}, language = {en}, - urldate = {2019-10-25}, - journal = {Fusion Engineering and Design}, - author = {Heuer, S. and Weber, Th. and Pintsuk, G. and Coenen, J. W. and Matejicek, J. and Linsmeier, Ch.}, + number = {11}, + urldate = {2021-11-15}, + author = {Lasa, A. and Blondel, S. and Bernholdt, D. E. and Canik, J. M. and Cianciosa, M. and Elwasif, W. R. and Green, D. L. and Roth, P. C. and Younkin, T. R. and Curreli, D. and Drobny, J. and Wirth, B. D.}, month = oct, - year = {2018}, - pages = {141--153}, - file = {Heuer et al. - 2018 - Aiming at understanding thermo-mechanical loads in.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YUS6HWPT\\Heuer et al. - 2018 - Aiming at understanding thermo-mechanical loads in.pdf:application/pdf}, + year = {2021}, + note = {Publisher: IOP Publishing}, + pages = {116051}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\JRQERAH6\\Lasa et al. - 2021 - Integrated model predictions on the impact of subs.pdf:application/pdf}, } -@article{delaporte-mathurin_finite_2019, - title = {Finite element analysis of hydrogen retention in {ITER} plasma facing components using {FESTIM}}, - volume = {21}, - copyright = {All rights reserved}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179119300547}, - doi = {10.1016/j.nme.2019.100709}, - abstract = {The behaviour of hydrogen isotopes in ITER monoblocks was studied using the code FESTIM (Finite Element Simulation of Tritium In Materials) which is introduced in this publication. FESTIM has been validated by reproducing experimental data and the Method of Manufactured Solutions was used for analytical verification. Following relevant plasma scenarios, both transient heat transfer and hydrogen isotopes (HIs) diffusion have been simulated in order to assess HIs retention in monoblocks. Relevant materials properties have been used. Each plasma cycle is composed of a current ramp up, a current plateau, a current ramp down and a resting phase before the following shot. 100 cycles are simulated. The total HIs inventory in the tokamak during resting phases reaches 1.8×10−3mg whereas during the implantation phases it keeps increasing as a power law of time. Particle flux on the cooling channel of the monoblock is also computed. The breakthrough time is estimated to be t=1×105s which corresponds to 24 cycles. Relevance of 2D modelling has been demonstrated by comparing the total HIs inventory obtained by 2D and 1D simulations. Using 1D simulations, a relative error is observed compared to 2D simulations which can reach -25\% during the resting phase. The error during implantation phases keeps increasing.}, +@article{harutyunyan_deuterium_2021, + title = {Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311521000714}, + doi = {10.1016/j.jnucmat.2021.152848}, + abstract = {The effect of He-induced defects in tungsten on the efficiency of trapping of deuterium ions in the subsurface layer was studied using thermal desorption spectroscopy (TDS). The W sample was pre-irradiated with 3 keV helium ions at room temperature and various fluences in the range of 1019 – 5 × 1021 He/m2. Then, it was exposed to a probe fluence of 1019 D/m2 of 2 keV D3+ (670 eV/D) ions, and in-situ TDS was performed. The de-trapping energy for D atoms increased with the increase of the He pre-irradiation fluence. On the other hand, a strong decrease in the D retention was observed if the He fluence increased above 1021 He/m2. At the highest He fluence of 5 × 1021 He/m2 deuterium trapping was possible only after partial release of He atoms. By comparison of experimental TDS spectra with modelling, the de-trapping energies of D atoms from various defects were estimated.}, language = {en}, - urldate = {2019-10-23}, - journal = {Nuclear Materials and Energy}, - author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, - month = dec, - year = {2019}, - pages = {100709}, - file = {Delaporte-Mathurin et al. - 2019 - Finite element analysis of hydrogen retention in I.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7SS9QGWF\\Delaporte-Mathurin et al. - 2019 - Finite element analysis of hydrogen retention in I.pdf:application/pdf}, -} - -@article{durif_impact_2019, - title = {Impact of tungsten recrystallization on {ITER}-like components for lifetime estimation}, - volume = {138}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618307026}, - doi = {10.1016/j.fusengdes.2018.11.003}, - abstract = {For ITER divertor, plasma facing components are made with tungsten as armor material. In previous papers, it has been shown that plasma facing components are prone to crack, appearing in tungsten block during thermal cyclic heat loading. In order to predict component lifetime, a numerical simulation is proposed in this paper. With regard to previous studies, tungsten (raw and recrystallized) real mechanical behaviors are taken into account. To be used as inputs for numerical simulations, compressive tests at different temperatures and strain rates were realized on raw and recrystallized tungsten. Raw tungsten tests reveal a linear elastic and ideal plastic behavior that is sensitive to strain rate. Concerning recrystallized tungsten, an elastic-viscoplastic behavior is observed on the entire explored temperature range (up to 1150 °C), that can be described by an elastic-plastic model with kinematic hardening. Manson-Coffin relationships are used to estimate the lifetime. When taking into account real mechanical behaviors for raw tungsten and recrystallized tungsten, we show that lifetime estimation is mainly driven by recrystallized thickness in the component, by the ductile to brittle transition temperature and finally by strain rate.}, - urldate = {2019-10-07}, - journal = {Fusion Engineering and Design}, - author = {Durif, A. and Richou, M. and Kermouche, G. and Lenci, M. and Bergheau, J-M.}, + urldate = {2021-02-08}, + journal = {Journal of Nuclear Materials}, + author = {Harutyunyan, Z. and Gasparyan, Yu. and Ryabtsev, S. and Efimov, V. and Ogorodnikova, O. and Pisarev, A. and Kanashenko, S.}, month = jan, - year = {2019}, - pages = {247--253}, - file = {Durif et al. - 2019 - Impact of tungsten recrystallization on ITER-like .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BMYRMN2V\\Durif et al. - 2019 - Impact of tungsten recrystallization on ITER-like .pdf:application/pdf}, + year = {2021}, + keywords = {TDS, binding energy, deuterium, helium, nuclear fusion, plasma-facing components, thermal desorption, tungsten}, + pages = {152848}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZUCWD5D3\\S0022311521000714.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\S38IIUZC\\S0022311521000714.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\P8FQTCV8\\S0022311521000714.html:text/html}, } -@article{ziegler_srim_2010, - series = {19th {International} {Conference} on {Ion} {Beam} {Analysis}}, - title = {{SRIM} – {The} stopping and range of ions in matter (2010)}, - volume = {268}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X10001862}, - doi = {10.1016/j.nimb.2010.02.091}, - abstract = {SRIM is a software package concerning the Stopping and Range of Ions in Matter. Since its introduction in 1985, major upgrades are made about every six years. Currently, more than 700 scientific citations are made to SRIM every year. For SRIM-2010, the following major improvements have been made: (1) About 2800 new experimental stopping powers were added to the database, increasing it to over 28,000 stopping values. (2) Improved corrections were made for the stopping of ions in compounds. (3) New heavy ion stopping calculations have led to significant improvements on SRIM stopping accuracy. (4) A self-contained SRIM module has been included to allow SRIM stopping and range values to be controlled and read by other software applications. (5) Individual interatomic potentials have been included for all ion/atom collisions, and these potentials are now included in the SRIM package. A full catalog of stopping power plots can be downloaded at www.SRIM.org. Over 500 plots show the accuracy of the stopping and ranges produced by SRIM along with 27,000 experimental data points. References to the citations which reported the experimental data are included.}, - number = {11}, - urldate = {2019-10-07}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Ziegler, James F. and Ziegler, M. D. and Biersack, J. P.}, - month = jun, - year = {2010}, - pages = {1818--1823}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YU9BMWW2\\Ziegler et al. - 2010 - SRIM – The stopping and range of ions in matter (2.pdf:application/pdf}, +@misc{noauthor_influence_nodate, + title = {Influence of exposure conditions on helium transport and bubble growth in tungsten {\textbar} {Scientific} {Reports}}, + url = {https://www.nature.com/articles/s41598-021-93542-9}, + urldate = {2021-11-10}, } -@article{ueda_baseline_2017, - title = {Baseline high heat flux and plasma facing materials for fusion}, - volume = {57}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Faa6b60}, - doi = {10.1088/1741-4326/aa6b60}, - abstract = {In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).}, +@article{arredondo_preliminary_2021, + title = {Preliminary estimates of tritium permeation and retention in the first wall of {DEMO} due to ion bombardment}, + volume = {28}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121001125}, + doi = {10.1016/j.nme.2021.101039}, + abstract = {Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling system, etc. Structural and plasma-facing components will act as a tritium sink, as tritium will be accumulated in the bulk of these components due to energetic particle bombardment and may permeate out of the vacuum system. The design of the plasma-facing components will consequently directly influence the plant lifetime, operational safety and cost of any future power plant. Therefore, modeling of tritium retention and permeation in these components is required for the engineering designs of the tritium breeding and safety systems. In this work, the diffusion-transport code TESSIM-X is benchmarked against the well-established TMAP7 code and a comparison with a simplified DEMO-relevant test case is performed. The use of either code for modeling of DEMO conditions is discussed. Following this, TESSIM-X is used to provide a preliminary assessment of tritium permeation and retention in the DEMO first wall, based on the current WCLL (Water Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed) breeding blanket designs.}, language = {en}, - number = {9}, - urldate = {2019-10-07}, - journal = {Nuclear Fusion}, - author = {Ueda, Y. and Schmid, K. and Balden, M. and Coenen, J. W. and Loewenhoff, Th and Ito, A. and Hasegawa, A. and Hardie, C. and Porton, M. and Gilbert, M.}, - month = jun, - year = {2017}, - pages = {092006}, - file = {Ueda et al. - 2017 - Baseline high heat flux and plasma facing material.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TAUSS4CR\\Ueda et al. - 2017 - Baseline high heat flux and plasma facing material.pdf:application/pdf}, + urldate = {2021-11-10}, + journal = {Nuclear Materials and Energy}, + author = {Arredondo, R. and Schmid, K. and Subba, F. and Spagnuolo, G. A.}, + month = sep, + year = {2021}, + keywords = {DEMO, Permeation, TMAP, First wall, Retention, TESSIM}, + pages = {101039}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\J7A87PRE\\S2352179121001125.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\65W4FVGT\\Arredondo et al. - 2021 - Preliminary estimates of tritium permeation and re.pdf:application/pdf}, } -@article{roache_code_2002, - title = {Code {Verification} by the {Method} of {Manufactured} {Solutions}}, - volume = {124}, - issn = {0098-2202}, - url = {https://asmedigitalcollection.asme.org/fluidsengineering/article/124/1/4/462791/Code-Verification-by-the-Method-of-Manufactured}, - doi = {10.1115/1.1436090}, +@article{noauthor_pre-conceptual_2021, + title = {Pre-conceptual design of an encapsulated breeder commercial blanket for the {STEP} fusion reactor}, + volume = {172}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/abs/pii/S0920379621006852}, + doi = {10.1016/j.fusengdes.2021.112909}, + abstract = {As part of the UKAEA Spherical Tokamak for Energy Production (STEP) fusion power station programme, a novel breeding blanket design was assessed. A co…}, language = {en}, - number = {1}, - urldate = {2019-10-07}, - journal = {Journal of Fluids Engineering}, - author = {Roache, Patrick J.}, - month = mar, - year = {2002}, - pages = {4--10}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RQV38CGQ\\Code-Verification-by-the-Method-of-Manufactured.html:text/html}, -} - -@article{dudson_verification_2016, - title = {Verification of {BOUT}++ by the method of manufactured solutions}, - volume = {23}, - issn = {1070-664X}, - url = {https://aip.scitation.org/doi/10.1063/1.4953429}, - doi = {10.1063/1.4953429}, - number = {6}, - urldate = {2019-10-07}, - journal = {Physics of Plasmas}, - author = {Dudson, B. D. and Madsen, J. and Omotani, J. and Hill, P. and Easy, L. and Løiten, M.}, - month = jun, - year = {2016}, - pages = {062303}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XXIKJDVY\\Dudson et al. - 2016 - Verification of BOUT++ by the method of manufactur.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QZENTZAZ\\1.html:text/html}, + urldate = {2021-10-26}, + journal = {Fusion Engineering and Design}, + month = nov, + year = {2021}, + note = {Publisher: North-Holland}, + pages = {112909}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NFPY3RNG\\S0920379621006852.html:text/html}, } -@article{alnaes_fenics_2015, - title = {The {FEniCS} {Project} {Version} 1.5}, - volume = {3}, - copyright = {Copyright (c) 2015 Archive of Numerical Software}, - issn = {2197-8263}, - url = {https://journals.ub.uni-heidelberg.de/index.php/ans/article/view/20553}, - doi = {10.11588/ans.2015.100.20553}, - abstract = {The FEniCS Project is a collaborative project for the development of innovative concepts and tools for automated scientific computing, with a particular focus on the solution of differential equations by finite element methods. The FEniCS Projects software consists of a collection of interoperable software components, including DOLFIN, FFC, FIAT, Instant, UFC, UFL, and mshr. This note describes the new features and changes introduced in the release of FEniCS version 1.5.}, +@incollection{kirby_finite_2012, + address = {Berlin, Heidelberg}, + series = {Lecture {Notes} in {Computational} {Science} and {Engineering}}, + title = {The finite element method}, + isbn = {978-3-642-23099-8}, + url = {https://doi.org/10.1007/978-3-642-23099-8_2}, + abstract = {The finite element method has emerged as a universal method for the solution of differential equations. Much of the success of the finite element method can be attributed to its generality and elegance, allowing a wide range of differential equations from all areas of science to be analyzed and solved within a common framework. Another contributing factor to the success of the finite element method is the flexibility of formulation, allowing the properties of the discretization to be controlled by the choice of approximating finite element spaces.}, language = {en}, - number = {100}, - urldate = {2019-10-07}, - journal = {Archive of Numerical Software}, - author = {Alnæs, Martin and Blechta, Jan and Hake, Johan and Johansson, August and Kehlet, Benjamin and Logg, Anders and Richardson, Chris and Ring, Johannes and Rognes, Marie E. and Wells, Garth N.}, - month = dec, - year = {2015}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DFTKYF4Q\\Alnæs et al. - 2015 - The FEniCS Project Version 1.5.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LU5SQ6FV\\20553.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZQF3NK8H\\Alnæs et al. - 2015 - The FEniCS Project Version 1.5.pdf:application/pdf}, + urldate = {2021-10-14}, + booktitle = {Automated {Solution} of {Differential} {Equations} by the {Finite} {Element} {Method}: {The} {FEniCS} {Book}}, + publisher = {Springer}, + author = {Kirby, Robert C. and Logg, Anders}, + editor = {Logg, Anders and Mardal, Kent-Andre and Wells, Garth}, + year = {2012}, + doi = {10.1007/978-3-642-23099-8_2}, + keywords = {Bilinear Form, Nodal Basis, Posteriori Error Estimate, Test Space, Variational Problem}, + pages = {77--94}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Z5K7BUDI\\Kirby et Logg - 2012 - The finite element method.pdf:application/pdf}, } -@article{longhurst_verification_2005, - title = {Verification and {Validation} of the {Tritium} {Transport} {Code} {TMAP7}}, - volume = {48}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST05-A967}, - doi = {10.13182/FST05-A967}, - abstract = {The TMAP code has been upgraded to version 7, which includes radioactive decay along with many features implemented in prior versions. Pursuant to acceptance and release for distribution, the code was exercised in a variety of problem types to demonstrate that it provides results in agreement with theoretical results for cases where those are available. It has also been used to model certain experimental results. In this paper, the capabilities of the TMAP7 code are demonstrated by presenting some of the results from the verification and validation process.}, - number = {1}, - urldate = {2019-10-07}, - journal = {Fusion Science and Technology}, - author = {Longhurst, Glen R. and Ambrosek, James}, - month = aug, - year = {2005}, - pages = {468--471}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QU7HWSBA\\FST05-A967.html:text/html}, +@article{boisse_modeling_2014, + title = {Modeling of the self trapping of helium and the trap mutation in tungsten using {DFT} and empirical potentials based on {DFT}}, + volume = {29}, + issn = {0884-2914, 2044-5326}, + url = {https://www.cambridge.org/core/journals/journal-of-materials-research/article/abs/modeling-of-the-self-trapping-of-helium-and-the-trap-mutation-in-tungsten-using-dft-and-empirical-potentials-based-on-dft/8E4976DED47CF5267DAEBEA9F8D84F9F}, + doi = {10.1557/jmr.2014.258}, + abstract = {, + Density functional theory calculations and molecular dynamics with a recently developed potential for W–He were used to evaluate the thermal stability of helium-vacancy clusters (nHe.mv) as well as pure interstitial helium clusters in tungsten. The stability of such objects results from a competitive process between thermal emission of vacancies, self interstitial atoms (SIAs), and helium, depending on the helium-to-vacancy ratio in mixed clusters or helium number in pure interstitial helium clusters. We investigated in particular the ground state configurations as well as the activation barriers of self trapping and trap mutation, i.e., the emission of one SIA along with the creation of one vacancy from a vacancy-helium or pure helium object.}, + language = {en}, + number = {20}, + urldate = {2021-01-22}, + journal = {Journal of Materials Research}, + author = {Boisse, J. and Backer, A. De and Domain, C. and Becquart, C. S.}, + month = oct, + year = {2014}, + note = {Publisher: Cambridge University Press}, + keywords = {helium, tungsten, custom, self trapping, simulation, trap mutation}, + pages = {2374--2386}, + file = {Boisse et al. - 2014 - Modeling of the self trapping of helium and the tr.pdf:D\:\\Logiciels\\data_zotero\\storage\\5WDXA55D\\Boisse et al. - 2014 - Modeling of the self trapping of helium and the tr.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\FJKQWK2W\\8E4976DED47CF5267DAEBEA9F8D84F9F.html:text/html}, } -@article{blondel_modeling_2017, - title = {Modeling {Helium} {Segregation} to the {Surfaces} of {Plasma}-{Exposed} {Tungsten} as a {Function} of {Temperature} and {Surface} {Orientation}}, - volume = {71}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST16-112}, - doi = {10.13182/FST16-112}, - abstract = {We provide a description of the dependence on surface crystallographic orientation and temperature of the segregation of helium implanted with energies consistent with low-energy plasma exposure to tungsten surfaces. Here, we describe multiscale modeling results based on a hierarchical approach to scale bridging that incorporates atomistic studies based on a reliable interatomic potential to parameterize a spatially dependent drift-diffusion-reaction cluster-dynamics code. An extensive set of molecular dynamics (MD) simulations has been performed at 933 K and/or 1200 K to determine the probabilities of desorption and modified trap mutation that occurs as small, mobile Hen (1 ≤ n ≤ 7) clusters diffuse from the near-surface region toward surfaces of varying crystallographic orientation due to an elastic interaction force that provides the thermodynamic driving force for surface segregation. These near-surface cluster dynamics have significant effects on the surface morphology, the near-surface defect structures, and the amount of helium retained in the material upon plasma exposure, for which we have developed an extensive MD database of cumulative evolution during high-flux helium implantation at 933 K, which we compare to our properly parameterized cluster-dynamics model. This validated model is then used to evaluate the effects of temperature on helium retention and subsurface helium clustering.}, - number = {1}, - urldate = {2019-10-07}, - journal = {Fusion Science and Technology}, - author = {Blondel, Sophie and Hammond, Karl D. and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, +@phdthesis{benannoune_simulations_2020, + type = {phdthesis}, + title = {Simulations {EF} du couplage entre diffusion et piégeage de l’hydrogène sous sollicitations thermomécaniques : {Applications} relatives au fer et au tungstène}, + shorttitle = {Simulations {EF} du couplage entre diffusion et piégeage de l’hydrogène sous sollicitations thermomécaniques}, + url = {https://tel.archives-ouvertes.fr/tel-03167860}, + abstract = {L‟objectif de ce travail de thèse est de reprendre les travaux précédents sur le couplage diffusion / plasticité sous Abaqus et d‟implémenter dans le code éléments finis un processus de piégeage transitoire dans une procédure utilisateur UMATHT, l‟équation de la chaleur dans une procédure UEL, et de modifier le comportement mécanique dans la procédure UMAT, afin de résoudre de manière couplée et simultanée les problèmes de diffusion/piégeage de l‟hydrogène soumis à des chargements thermomécaniques.Le modèle ainsi développé avec un couplage diffusion/piégeage transitoire a été confronté dans un premier temps, et validé sur plusieurs matériaux (tungstène et fer) par des comparaisons sur des cas tests avec d‟autres codes de la littérature (notamment le code MRE HIIPC). Puis, en considérant les variations des champs thermiques, l‟outil et l‟implémentation ont été validées sur des résultats expérimentaux de TDS sur du tungstène ainsi que sur d‟autres codes de la littérature sur le fer.Enfin, le modèle entièrement couplé a ainsi été utilisé sur des applications de chargements thermiques complexes sur une composante du futur tokamak d‟ITER (DFW). Les simulations 3D sur cette structure ont mis en évidence les effets de géométrie qui ne peuvent être pris en compte dans des simulations 1D. Elles ont permis de mettre également en exergue le rôle de la pression hydrostatique, la prise en compte de la dilatation thermique pouvant induire des écarts importants sur les résultats.}, + language = {fr}, + urldate = {2021-10-12}, + school = {Université Paris-Nord - Paris XIII}, + author = {Benannoune, Sofiane}, month = jan, - year = {2017}, - pages = {22--35}, -} - -@misc{gallo_surface_2014, - type = {Laurea {Magistrale} / {Specialistica}}, - title = {Surface modifications and deuterium retention of tungsten and tungsten oxide thin films after high flux deuterium plasma exposure}, - url = {https://www.politesi.polimi.it/handle/10589/94446}, - abstract = {PASSONI, MATTEO}, - language = {eng}, - urldate = {2019-10-07}, - author = {GALLO, ALBERTO}, - month = jul, - year = {2014}, + year = {2020}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3LW8DVYD\\Benannoune - 2020 - Simulations EF du couplage entre diffusion et piég.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ELLJWPT5\\tel-03167860.html:text/html;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YHLDLPKY\\tel-03167860.html:text/html}, } -@phdthesis{addab_formation_2016, - type = {thesis}, - title = {Formation, caractérisation et bombardements ioniques de films minces de {WO3} d'intérêt pour la fusion magnétique}, - url = {http://www.theses.fr/2016AIXM4765}, - abstract = {Dans ce travail, nous étudions la stabilité thermique et les effets des irradiations par un plasma d'hélium ou de deutérium de films minces de WO3 d’intérêt pour la fusion magnétique (projet ITER). L’objectif est de comprendre comment une oxydation du divertor modifie les interactions plasma paroi. Pour cela, nous avons synthétisé des films de WO3 par oxydation thermique de substrats de W à 400°C et caractérisé les effets du type de substrat, de la pression d’oxygène et du temps d’oxydation sur la structure et sur l’épaisseur des oxydes formés. La structure (monoclinique nanocristalline), la morphologie et les défauts des échantillons ont été analysés avant et après traitement, à différentes échelles, en utilisant la microscopie électronique, la microscopie Raman, la diffraction de rayons X, et la microscopie à force atomique.Le chauffage sous vide (400 - 800°C) a conduit à la formation de WO2. Le bombardement aux ions D+ (11 eV) a mené à une diffusion profonde du deutérium à travers le film d’oxyde, engendrant un effet électrochimique, observé ici pour la première fois sous irradiation plasma. Cet effet, réversible, est associé à la formation de bronzes de tungstène (DxWO3) et à une transition de phase vers une structure hexagonale. Des bombardements aux ions He+ (20 eV) ont été réalisés afin de dissocier les effets physiques et chimiques. A température ambiante, le bombardement a causé peu de changements morphologiques et structuraux. Par contre, le autre bombardement à 400°C a causé une érosion du film d’oxyde accompagnée d’un changement de couleur, une amorphisation en surface et la formation de bulles à l’interface W / WO3.}, - urldate = {2019-10-07}, - school = {Aix-Marseille}, - author = {Addab, Younes}, +@article{montupet-leblond_permeation_2021, + title = {Permeation and trapping of hydrogen in {Eurofer97}}, + volume = {29}, + copyright = {All rights reserved}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121001290}, + doi = {10.1016/j.nme.2021.101062}, + abstract = {Diffusion and trapping of hydrogen isotopes in fusion materials need to be fully described in order to evaluate permeation and retention in fusion reactors walls and breeding blankets. Hydrogen gas permeation experiments have been conducted on Eurofer97 with pressures ranging from 101 to 105 Pa and temperatures between 473 K and 673 K, resulting in solubility K(T) (mol m−3 Pa−12)= 1.76⋅10−1exp(−0.27(eV)kBT), diffusivity D(T) (m2 s−1) =2.52⋅10−7exp(−0.16(eV)kBT) and permeability Φ(T) (mol m−1 Pa−12 s−1) =4.43⋅10−8exp(−0.43(eV)kBT). Trapping parameters have been investigated using thermal desorption spectrometry of deuterium-loaded samples coupled with parametric optimization, leading to detrapping energies Edt,1=0.51eV, Edt,2=1.27eV, Edt,3=1.65eV and densities Nt,1=6.01⋅1025 m−3, Nt,2=6.44⋅1022 m−3, Nt,3=3.88⋅1023 m−3. This parametric optimization is performed using a kinetic surface model: the contribution of this model is compared to the results given by solubility and recombination rate models.}, + journal = {Nuclear Materials and Energy}, + author = {Montupet-Leblond, Floriane and Hodille, E. A. and Vartanian, S. and Payet, M. and Delaporte-Mathurin, R. and Mougenot, J. and Charles, Y. and Bernard, E. and Grisolia, C.}, month = dec, - year = {2016}, - file = {Addab - 2016 - Formation, caractérisation et bombardements ioniqu.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6RMYKZ58\\Addab - 2016 - Formation, caractérisation et bombardements ioniqu.pdf:application/pdf}, + year = {2021}, + keywords = {Hydrogen, Permeation, Eurofer97, MHIMS, Surfaces, Thermal desorption spectrometry, Trapping}, + pages = {101062}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\JIXQCGKX\\S2352179121001290.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EB7E997C\\S2352179121001290.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DC624WFY\\S2352179121001290.html:text/html}, } -@inproceedings{huang_tungsten_2016, - title = {Tungsten monoblock concepts for the {FNSF} first wall and divertor}, - abstract = {Next-step fusion nuclear devices require plasma-facing components that can survive a much higher neutron dose than ITER, and in many design concepts also require higher operating temperatures, higher reliability, and materials with more attractive safety and environmental characteristics. In search of first wall concepts that can withstand surface heat fluxes beyond 2 MW/m, we analyzed advanced “monoblock” designs using coolants and materials that offer more attractive long-term performance. These use tungsten armor and heat sinks, similar to previous designs, but replace the coolant with helium and the coolant containment pipe with either low-activation ferritic-martensitic steel or SiC/SiC composite. The results of analysis show that helium-cooled steel can remove up to 5 MW/m of steady-state surface heat flux and helium-cooled SiC/SiC can remove nearly 10 MW/m while satisfying all materials and design requirements. This suggests that a He-cooled W/SiC monoblock could withstand divertor-like heat fluxes.}, - author = {Huang, Yan and Tillack, Mark S. and Ghoniem, Nasr M.}, - year = {2016}, - file = {Huang et al. - 2016 - Tungsten monoblock concepts for the FNSF first wal.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MGSBJ3Z9\\Huang et al. - 2016 - Tungsten monoblock concepts for the FNSF first wal.pdf:application/pdf}, +@article{hodille_modelling_2021-1, + title = {Modelling tritium adsorption and desorption from tungsten dust particles with a surface kinetic model}, + issn = {0029-5515}, + url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac0f37}, + doi = {10.1088/1741-4326/ac0f37}, + abstract = {A kinetic surface model is presented and used to explain the loading and desorption kinetics of tritium retained in micrometre-sized tungsten (W) dust particles. The model describes the sticking of hydrogen isotopes from the gas phase to W surfaces and the desorption from W surfaces. The initial sticking coefficient is set to one and independent of the temperature. The activation energy for desorption depends on the hydrogen coverage of the surface and is parametrised with density functional theory (DFT) calculations for W(100), W(110), and W(111) surface. The DFT-parametrised model is successfully compared to experimental results showing that the amount of measured tritium as well as the desorption kinetic can be modelled with only tritium adsorbed on the surface of W dust particles. Then, the model is used to explore possible scenarios to remove the tritium from the W surfaces by exposing the tritiated surfaces to either deuterium and hydrogen. The simulations suggest that it can be possible to remove all the tritium trapped on the W surfaces even at room temperature as soos as the hydrogen or deuterium pressure is higher than the tritium pressure. This gives opportunity to build tritium removal scenarios for ITER.}, + language = {en}, + urldate = {2021-06-29}, + journal = {Nuclear Fusion}, + author = {Hodille, Etienne Augustin and Payet, Mickael and Marascu, Valentina and Peillon, Samuel and Mougenot, Jonathan and Ferro, Yves and Delaporte-Mathurin, Rémi and Leblond, Floriane and Bernard, Elodie and Grisolia, Christian}, + year = {2021}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\D9LARE6K\\Hodille et al. - 2021 - Modelling tritium adsorption and desorption from t.pdf:application/pdf}, } -@article{crescenzi_iter-like_2017, - series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, - title = {{ITER}-like divertor target for {DEMO}: {Design} study and fabrication test}, - volume = {124}, - issn = {0920-3796}, - shorttitle = {{ITER}-like divertor target for {DEMO}}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379617300972}, - doi = {10.1016/j.fusengdes.2017.02.014}, - abstract = {As a major in-vessel component of a tokamak-type fusion reactor, the divertor is mainly in charge of removal of particles and partial power exhaust via scrape-off layer. The target plate of the divertor is directly exposed to non-uniform high heat flux on the surface by particle bombardment and radiation. In the case of ITER and a DEMO reactor, the peak surface heat flux is expected to reach up to 10MW/m2 during normal operation and 20MW/m2 during slow transient events like loss of plasma detachment. This paper reports the results of a preliminary code-based design study and fabrication technology verification test which were conducted for developing an ITER-like divertor target design for the DEMO divertor. The structural failure evaluation against the ratchetting and fatigue criteria of the ITER SDC-IC showed that the design with reduced dimensions would allow sufficient design margin (reserve factor) for three distinct thermal loading cases. The first trial of mock-up fabrication using a new joining furnace at ENEA was successfully completed. The ultrasonic inspection test made before and after the cyclic HHF tests at GLADIS facility demonstrated high quality of fabrication and robust design concept.}, - urldate = {2019-10-07}, - journal = {Fusion Engineering and Design}, - author = {Crescenzi, F. and Greuner, H. and Roccella, S. and Visca, E. and You, J. H.}, - month = nov, - year = {2017}, - pages = {432--436}, - file = {Crescenzi et al. - 2017 - ITER-like divertor target for DEMO Design study a.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L76P4XA7\\Crescenzi et al. - 2017 - ITER-like divertor target for DEMO Design study a.pdf:application/pdf}, +@misc{noauthor_permeation_nodate, + title = {Permeation and trapping of hydrogen in {Eurofer97} - {ScienceDirect}}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121001290?via%3Dihub}, + urldate = {2021-10-07}, + file = {Permeation and trapping of hydrogen in Eurofer97 - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\I34P7J9H\\S2352179121001290.html:text/html}, } -@article{bakaev_ab_2020, - title = {Ab initio study of the stability of {H}-{He} clusters at lattice defects in tungsten}, - volume = {478}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X20303153}, - doi = {10.1016/j.nimb.2020.06.033}, - abstract = {The interaction of a H-He pair embedded in various types of lattice defects in the bcc tungsten, such as vacancies, tilt grain boundaries, a core of screw and edge dislocations has been studied using ab initio calculations. It is shown that H-vacancy and He-vacancy clusters are weaker traps for He and H single atoms, respectively, as compared to a single vacancy. H or He atom, solely, is strongly attracted to the studied grain boundary interfaces, while the mutual H-He interaction is negligible (close to the interaction in vacuum) if both atoms are placed in the adjacent trapping sites located on the grain boundary. The H-He pair placed in the core of the screw or edge dislocation exhibits the binding energy of {\textasciitilde}0.2–0.3 eV, which is close to the H-He attraction in the bulk W. The ground-state configurations for H-He dimers located in various lattice defects in W were rationalized on the basis of atomic structure visualizations, bond analysis and charge density distributions. The obtained data are discussed in the frame of the thermal desorption spectroscopy results offering a better understanding of the detrapping stages of He and H isotopes under mixed plasma exposure conditions.}, +@article{bergstrom_mobility_2021, + title = {The mobility of small, over-pressurized helium bubbles in tungsten at 2000 {K}}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311521005298}, + doi = {10.1016/j.jnucmat.2021.153306}, + abstract = {Fusion reactor environments inevitably lead to the formation of high-pressure helium bubbles whose nucleation, growth, and diffusion strongly impact the performance of plasma-facing components. This research describes a diffusion mechanism of over-pressurized bubbles via a sequence of Frenkel pair nucleation, self-interstitial migration, and Frenkel pair annihilation. Molecular dynamics was used to simulate the diffusion of small bubbles in tungsten at 2000 K with helium-per-vacancy ratios in the range of 4.5 to 7. The diffusion coefficients are calculated and their dependence on helium content, number of vacancies, and number of attached self-interstitials is characterized. It is found that bubbles are most mobile when the nucleation/annihilation rates of Frenkel pairs are nearly equal and when the bubbles nucleate and annihilate a single self-interstitial. All bubbles experience a peak diffusivity, which can be as high as 10−11 m2/s decreasing with bubble size. The calculated diffusion coefficients provide valuable insight into the mobility of small, high-pressure bubbles, and can be used as input parameters in mesoscale models to improve predictions of plasma-surface interactions. (LA-UR-21-21881)}, language = {en}, - urldate = {2020-12-04}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Bakaev, Alexander and Terentyev, Dmitry and Zhurkin, Evgeny E.}, + urldate = {2021-09-28}, + journal = {Journal of Nuclear Materials}, + author = {Bergstrom, Z. J. and Perez, D. and Martínez, E.}, month = sep, - year = {2020}, - keywords = {Dislocations, Grain boundaries, Helium, Hydrogen, Tungsten}, - pages = {269--273}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EJEYFQKI\\S0168583X20303153.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U83DFHUG\\Bakaev et al. - 2020 - Ab initio study of the stability of H-He clusters .pdf:application/pdf}, + year = {2021}, + keywords = {Tungsten, Diffusion, Bubbles, Helium}, + pages = {153306}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\U7Q6AYE5\\S0022311521005298.html:text/html}, } -@article{ying_recent_2020, - title = {Recent advances in tritium modeling and its implications on tritium management for outer fuel cycle}, - volume = {161}, +@article{fausser_tokamak_2012, + series = {Tenth {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-10)}, + title = {Tokamak {D}-{T} neutron source models for different plasma physics confinement modes}, + volume = {87}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620304439}, - doi = {10.1016/j.fusengdes.2020.111895}, - abstract = {Recent advances in tritium transport modeling of helium-cooled ceramic breeding blankets systems has shined light into some tritium management issues. A detailed component model accounting for multi-physics, design, and operational features is necessary to provide accurate estimations of tritium permeation rates to the building/environment- a safety and licensing concern for a fusion nuclear reactor. We found that tritium permeation to buildings can be reduced of ∼20 times when H2 is increased from ∼0.2 Pa to 100 Pa in coolant streams due to the effect of H and T co-permeation. Similarly, the practice of adding about 0.1 \% vol of H2 into the helium purge gas to promote tritium release can also reduce permeation from breeding zones to coolant systems. However, high H2 partial pressure in helium purge gas further complicates tritium extraction methodology, and may compromise extraction efficiency. This paper provides a concentrated analysis of tritium management in the He-cooled ceramic blankets with the goal of providing further outer fuel cycle tritium R\&D guidance from an integrated point of view.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379612000853}, + doi = {10.1016/j.fusengdes.2012.02.025}, + abstract = {Neutronic studies of European demonstration fusion power plant (DEMO) have been so far based on plasma physics low confinement mode (L-mode). Future tokamaks, nevertheless, may likely use alternative confinement modes such as high or advanced confinement modes (H\&A-mode). Based on analytical formulae used in plasma physics, H\&A-modes D-T neutron sources formulae are proposed in this paper. For that purpose, a tokamak random neutron source generator, TRANSGEN, has been built generating bidimensional (radial and poloidal) neutron source maps to be used as input for neutronics Monte-Carlo codes (TRIPOLI-4 and MCNP5). The impact of such a source on the neutronic behavior of the European DEMO-2007 Helium-cooled lithium–lead reactor concept has been assessed and compared with previous results obtained using a L-mode neutron source. An A-mode neutron source map from TRANSGEN has been used with the code TRIPOLI-4. Assuming the same fusion power, results show that main reactor global neutronic parameters, e.g. tritium breeding ratio and neutron multiplication factor, evolved slightly when compared to present uncertainties margin. However, local parameters, such as the neutron wall loading (NWL), change significantly compared to L-mode shape: from −22\% to +11\% for NWL.}, language = {en}, - urldate = {2020-12-04}, + number = {5}, + urldate = {2021-09-21}, journal = {Fusion Engineering and Design}, - author = {Ying, Alice and Riva, Marco and Ahn, Mu-Young and Moreno, Carlos and Cristescu, Ion}, - month = dec, - year = {2020}, - keywords = {Test blanket system, Tritium extraction systems, Tritium management, Tritium permeation, Tritium transport}, - pages = {111895}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EXV8JWIM\\S0920379620304439.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BU4MRWY2\\Ying et al. - 2020 - Recent advances in tritium modeling and its implic.pdf:application/pdf}, -} - -@unpublished{delaporte-mathurin_parametric_nodate, - type = {Submitted to {Nuclear} {Materials} and {Energy}}, - title = {Parametric optimisation based on {TPD} experiments for rapid and efficient identification of hydrogen transport materials properties}, - copyright = {All rights reserved}, - author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, + author = {Fausser, Clement and Puma, Antonella Li and Gabriel, Franck and Villari, Rosaria}, + month = aug, + year = {2012}, + keywords = {DEMO, Neutronics, Plasma source description, TRIPOLI-4}, + pages = {787--792}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ARCDKAPY\\S0920379612000853.html:text/html}, } -@article{gilbert_integrated_2012, - title = {An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation}, - volume = {52}, - issn = {0029-5515}, - shorttitle = {An integrated model for materials in a fusion power plant}, - url = {https://doi.org/10.1088%2F0029-5515%2F52%2F8%2F083019}, - doi = {10.1088/0029-5515/52/8/083019}, - abstract = {The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. As well as producing defects, the neutrons bombarding the materials initiate nuclear reactions, leading to transmutation of the elemental atoms. Products of many of these reactions are gases, particularly helium, which can cause swelling and embrittlement of materials. This paper integrates several different computational techniques to produce a comprehensive picture of the response of materials to neutron irradiation, enabling the assessment of structural integrity of components in a fusion power plant. Neutron-transport calculations for a model of the next-step fusion device DEMO reveal the variation in exposure conditions in different components of the vessel, while inventory calculations quantify the associated implications for transmutation and gas production. The helium production rates are then used, in conjunction with a simple model for He-induced grain-boundary embrittlement based on electronic-structure density functional theory calculations, to estimate the timescales for susceptibility to grain-boundary failure in different fusion-relevant materials. There is wide variation in the predicted grain-boundary-failure lifetimes as a function of both microstructure and chemical composition, with some conservative predictions indicating much less than the required lifetime for components in a fusion power plant.}, +@article{noauthor_thermal_nodate, + title = {Thermal damage of tungsten-armored plasma-facing components under high heat flux loads}, language = {en}, - number = {8}, - urldate = {2020-11-30}, - journal = {Nuclear Fusion}, - author = {Gilbert, M. R. and Dudarev, S. L. and Zheng, S. and Packer, L. W. and Sublet, J.-Ch}, - month = aug, - year = {2012}, - note = {Publisher: IOP Publishing}, - pages = {083019}, - file = {Gilbert et al. - 2012 - An integrated model for materials in a fusion powe.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ACCAWEYS\\Gilbert et al. - 2012 - An integrated model for materials in a fusion powe.pdf:application/pdf}, + pages = {10}, + file = {Thermal damage of tungsten-armored plasma-facing c.pdf:D\:\\Logiciels\\data_zotero\\storage\\K7XMJP3U\\Thermal damage of tungsten-armored plasma-facing c.pdf:application/pdf}, } -@article{gilbert_neutron-induced_2013, - series = {{FIFTEENTH} {INTERNATIONAL} {CONFERENCE} {ON} {FUSION} {REACTOR} {MATERIALS}}, - title = {Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials}, - volume = {442}, +@article{iwakiri_effects_2002, + title = {Effects of helium bombardment on the deuterium behavior in tungsten}, + volume = {307-311}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311513005886}, - doi = {10.1016/j.jnucmat.2013.03.085}, - abstract = {In a fusion reactor materials will be subjected to significant fluxes of high-energy neutrons. As well as causing radiation damage, the neutrons also initiate nuclear reactions leading to changes in the chemical composition of materials (transmutation). Many of these reactions produce gases, particularly helium, which cause additional swelling and embrittlement of materials. This paper investigates, using a combination of neutron-transport and inventory calculations, the variation in displacements per atom (dpa) and helium production levels as a function of position within the high flux regions of a recent conceptual model for the ‘next-step’ fusion device DEMO. Subsequently, the gas production rates are used to provide revised estimates, based on new density-functional-theory results, for the critical component lifetimes associated with the helium-induced grain-boundary embrittlement of materials. The revised estimates give more optimistic projections for the lifetimes of materials in a fusion power plant compared to a previous study, while at the same time indicating that helium embrittlement remains one of the most significant factors controlling the structural integrity of fusion power plant components.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311502011789}, + doi = {10.1016/S0022-3115(02)01178-9}, + abstract = {The effects of pre-irradiation with helium ions of fusion relevant energy on trapping of injected deuterium in W was studied by thermal desorption spectrometry technique using high-resolution quadrupole mass spectrometer. Pre-irradiation with He ions caused remarkable effects on the trapping of injected deuterium. Most of the injected deuterium is desorbed between 400 and 600 K for the case without helium pre-irradiation, while additional desorption occurs between 600 and 800 K for the helium pre-irradiation case. Total amount of the trapped deuterium for irradiations of 2.0×1021 He/m2 and 1.0×1022 D2/m2 is 6.2×1020 D2/m2, which is more than three times higher than that in the case of no helium pre-irradiation. The present result indicates that irradiation effects of He bombardment must be taken into account to understand and evaluate the behavior of hydrogen isotopes in fusion environment.}, language = {en}, - number = {1, Supplement 1}, - urldate = {2020-11-30}, + urldate = {2019-11-04}, journal = {Journal of Nuclear Materials}, - author = {Gilbert, M. R. and Dudarev, S. L. and Nguyen-Manh, D. and Zheng, S. and Packer, L. W. and Sublet, J. -Ch.}, - month = nov, - year = {2013}, - pages = {S755--S760}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TL89TGW9\\S0022311513005886.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L3U3WSSS\\Gilbert et al. - 2013 - Neutron-induced dpa, transmutations, gas productio.pdf:application/pdf}, + author = {Iwakiri, H. and Morishita, K. and Yoshida, N.}, + month = dec, + year = {2002}, + keywords = {Experiment}, + pages = {135--138}, + file = {Iwakiri et al. - 2002 - Effects of helium bombardment on the deuterium beh.pdf:D\:\\Logiciels\\data_zotero\\storage\\K946CAHJ\\Iwakiri et al. - 2002 - Effects of helium bombardment on the deuterium beh.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\HWM3T2A9\\S0022311502011789.html:text/html}, } -@article{zhou_growth_2019, - title = {The growth and release of helium bubbles near tungsten surface studied with molecular dynamics simulations}, - volume = {455}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X1930446X}, - doi = {10.1016/j.nimb.2019.06.023}, - abstract = {The growth and release processes of helium bubbles near tungsten surface have been investigated by molecular dynamics (MD) simulations. The results indicate that the surface morphologies are dependent on orientation of surfaces. Before bubble rupture occurs, stepped, thin schistose and pyramidal structures are observed on the (1 1 0), (1 0 0) and (1 1 1) surfaces, respectively. When the angle between the normal direction of surface and the sliding direction (〈1 1 1〉 direction) is larger, flatter surface would be formed and the subsequent release process would be more violent. In the bursting process, the release rate of helium and the degree of surface damage are correlated with the surface stacking height before bubble bursts. Unrepaired crack structures have been observed on the (1 1 0) and (1 0 0) surfaces, while a smaller hole on the (1 1 1) surface. The stacking atoms have a tendency to make the surface restore to the bcc structure. At high temperature, the surface pore with radius ∼1 nm can be self-healed from outer to inner by the diffusion of surface atoms, while no recovery is observed in MD time scale when the ratio of He/V in the bubble is high.}, +@article{wang_effect_2021, + title = {Effect of helium pre-implantation on the thermal shock performance of tungsten}, + volume = {27}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121000272}, + doi = {10.1016/j.nme.2021.100934}, + abstract = {In ITER and future tokamaks, high heat flux loads will lead to recrystallization and decrease in toughness and thermal shock resistance of tungsten plasma facing materials, resulting in crack network formation and possible failure. In this study, thermal shock tests of blank, helium-plasma-exposed and helium-ion-irradiated rolled tungsten with/without isothermal annealing are conducted. Without annealing, cracks start to form in blank tungsten at the power density of 0.35 GW/m2, while no cracks are observed on the loaded surface of helium-plasma-exposed and helium-ion-irradiated ones. After annealing at 1473 K for 1 h, the recrystallization fractions of the three kinds of tungsten are around 50\%, 18\% and 8\%, respectively. The following thermal shock tests of the annealed samples show that the cracking thresholds of blank and helium-plasma-exposed ones reduce to 0.3 GW/m2, while cracks do not appear in the helium-ion-irradiated one at this power density. Surface roughening thresholds are also improved in helium pre-implanted samples and do not change after annealing. It indicates that both helium plasma and ion irradiation improve the thermal stability and damaging threshold of tungsten, and helium ion irradiation has a stronger influence. This suggests a potential benefit of helium to extend the service lifetime of tungsten.}, language = {en}, - urldate = {2020-01-10}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Zhou, Yulu and Yuan, Chiwen and Li, Tao and Tao, Xiaoma and Ouyang, Yifang}, - month = sep, - year = {2019}, - keywords = {Molecular Dynamics, Bursting, Tungsten, Helium bubble, Molecular dynamics simulations, Self-healing, Surface morphology}, - pages = {66--73}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6QYWAS86\\Zhou et al. - 2019 - The growth and release of helium bubbles near tung.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H2BYWYR3\\S0168583X1930446X.html:text/html}, + urldate = {2021-04-22}, + journal = {Nuclear Materials and Energy}, + author = {Wang, Yingdi and Guo, Wangguo and Zhu, Yida and Yuan, Yue and Peng, Jiaguan and Ren, Mengchong and Wang, Zheng and Cheng, Long and Chen, Zhe and Lian, Youyun and Liu, Xiang and Lu, Guang-Hong}, + month = jun, + year = {2021}, + keywords = {Helium, Recrystallization retarding, Surface cracking, Surface roughening, Thermal shocks}, + pages = {100934}, + annote = {Helium can IN SOME CONDITIONS have positive effects on W: thermal shock resistance, recrystalisation }, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5W7KSTVY\\Wang et al. - 2021 - Effect of helium pre-implantation on the thermal s.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9KXAR29U\\S2352179121000272.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DHD3XS3T\\S2352179121000272.html:text/html}, } -@article{jiangfeng_one-dimensional_2011, - title = {One-dimensional simulation of hydrogen isotopes diffusion in composite materials by {FVM}}, - volume = {36}, - issn = {0360-3199}, - url = {http://www.sciencedirect.com/science/article/pii/S0360319911003570}, - doi = {10.1016/j.ijhydene.2011.02.040}, - abstract = {Tritium diffusion and permeation in construct materials is one of the most important problems in fusion material research. For the tritium concentration evaluation within each sub-system of the fuel cycle of ITER, a finite volume computer program was developed for diffusion analysis of hydrogen isotopes in composite materials. The program calculates hydrogen isotope concentration distributions through composite materials such as tritium permeation barriers as function of the applied boundary conditions. The program can simulate hydrogen isotopes diffusion through single materials and composite materials in one-dimensional and can also make the output visualization. We look forward to making some comparison calculation for the present calculation with TMAP.}, +@article{urgorri_influence_2021, + title = {The influence of {MHD} boundary layers on tritium permeation in {PbLi} flows for fusion breeding blankets}, + volume = {181}, + issn = {0017-9310}, + url = {https://www.sciencedirect.com/science/article/pii/S0017931021010115}, + doi = {10.1016/j.ijheatmasstransfer.2021.121906}, + abstract = {In PbLi based breeding blanket concepts, tritium is produced inside the liquid metal and drag out of the reactor by the liquid metal flow. However, undesired permeation through the channels and pipes walls occurs spontaneously since tritium naturally diffuses in the opposite direction of the concentration gradient. This way tritium can reach the blanket coolant circuit or even the exterior with an impact on the tritium self-sustainability and the safety of the plant. Similarly to heat transfer processes, permeation through the walls in the interface between the flow and the steel is mostly affected by the dynamics of the boundary layers. This is ruled by the electrical coupling between the moving conductor and the conducting walls as a result of the Magnetohydrodynamics (MHD) interactions which dominate the flow dynamics. In this work, the connection between the MHD forces and tritium transport is numerically studied using the simulation platform ANSYS-Fluent. The velocity profiles of a PbLi test channel have been firstly computed in a wide range of Hartmann numbers from 102 to 104. These velocity profiles are then applied to a 3D tritium transport model developed with the customization capabilities of the same platform. A series of tritium transport simulations are carried out considering different permeation regimes: surface-limited, diffusion-limited and intermediate regimes. The development of the concentration boundary layers along the channel is studied in different permeation regimes, magnetic fields and velocity fields. This has allowed correlating the Sherwood number (Sh) with the Hartmann (Ha), Reynolds (Re) and permeation numbers (W).}, language = {en}, - number = {9}, - urldate = {2020-10-22}, - journal = {International Journal of Hydrogen Energy}, - author = {Jiangfeng, Song and Zhiyong, Huang and Lianxia, Li and Chang'an, Chen and Deli, Luo}, - month = may, - year = {2011}, - keywords = {Composite materials, Diffusion, Finite Volume Method (FVM), Hydrogen isotope}, - pages = {5702--5706}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PVHLIT63\\Jiangfeng et al. - 2011 - One-dimensional simulation of hydrogen isotopes di.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LBQ9GGTM\\S0360319911003570.html:text/html}, + urldate = {2021-09-07}, + journal = {International Journal of Heat and Mass Transfer}, + author = {Urgorri, F. R. and Moreno, C. and Fernández-Berceruelo, I. and Rapisarda, D.}, + month = dec, + year = {2021}, + keywords = {Tritium transport, Mass transfer, Breeding blanket, Magnetohydrodynamics}, + pages = {121906}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QRJ9KMNE\\S0017931021010115.html:text/html}, } -@article{elmukashfi_modelling_2020, - title = {A modelling framework for coupled hydrogen diffusion and mechanical behaviour of engineering components}, - volume = {66}, - issn = {1432-0924}, - url = {https://doi.org/10.1007/s00466-020-01847-9}, - doi = {10.1007/s00466-020-01847-9}, - abstract = {In this paper, we propose a finite element formulation for solving coupled mechanical/diffusion problems. In particular, we study hydrogen diffusion in metals and its impact on their mechanical behaviour (i.e. hydrogen embrittlement). The formulation can be used to model hydrogen diffusion through a material and its accumulation within different microstructural features of the material (dislocations, precipitates, interfaces, etc.). Further, the effect of hydrogen on the plastic response and cohesive strength of different interfaces can be incorporated. The formulation adopts a standard Galerkin method in the discretisation of both the diffusion and mechanical equilibrium equations. Thus, a displacement-based finite element formulation with chemical potential as an additional degree of freedom, rather than the concentration, is employed. Consequently, the diffusion equation can be expressed fundamentally in terms of the gradient in chemical potential, which reduces the continuity requirements on the shape functions to zero degree, \$\$\{{\textbackslash}mathcal \{C\}\}\_\{0\}\$\$C0, i.e. linear functions, compared to the \$\$\{{\textbackslash}mathcal \{C\}\}\_\{1\}\$\$C1continuity condition required when concentration is adopted. Additionally, a consistent interface element formulation can be achieved due to the continuity of the chemical potential across the interface—concentration can be discontinuous at an interface which can lead to numerical problems. As a result, the coding of the FE equations is more straightforward. The details of the physical problem, the finite element formulation and constitutive models are initially discussed. Numerical results for various example problems are then presented, in which the efficiency and accuracy of the proposed formulation are explored and a comparison with the concentration-based formulations is presented.}, +@article{ciraolo_first_2019, + title = {First modeling of strongly radiating {WEST} plasmas with {SOLEDGE}-{EIRENE}}, + volume = {20}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179118302461}, + doi = {10.1016/j.nme.2019.100685}, + abstract = {We present first results of SOLEDGE-EIRENE modeling a strongly radiating plasma in the WEST tokamak. Using measurements from a reciprocating Langmuir probe we have determined the SOLEDGE input parameters, i.e. separatrix density at outboard midplane and radial transport coefficients typical of L-mode plasma. We have performed deuterium plasma simulations with presence of oxygen, injected from the core boundary into the simulation domain. The comparison between the radiated power measured from the bolometry in the divertor region and the one computed from SOLEDGE simulations seems to indicate a concentration of oxygen of about 2\%. Moreover we have obtained good agreement between simulation results and experimental measurements on electron density and electron temperature profiles at the outer strike point. First qualitative analysis of spectroscopic synthetic diagnostic on Dα signals is also presented.}, language = {en}, - number = {1}, - urldate = {2020-10-22}, - journal = {Computational Mechanics}, - author = {Elmukashfi, Elsiddig and Tarleton, Edmund and Cocks, Alan C. F.}, - month = jul, - year = {2020}, - pages = {189--220}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\AZWPS2ET\\Elmukashfi et al. - 2020 - A modelling framework for coupled hydrogen diffusi.pdf:application/pdf}, + urldate = {2021-09-06}, + journal = {Nuclear Materials and Energy}, + author = {Ciraolo, G. and Thin, A. and Bufferand, H. and Bucalossi, J. and Fedorczak, N. and Gunn, J. P. and Pascal, J. Y. and Tamain, P. and Gil, C. and Gouin, A. and Meyer, O. and Devynck, P. and Vartanian, S. and Klepper, C. C. and Serre, E. and Nespoli, F. and Gallo, A. and Marandet, Y. and Rosato, J.}, + month = aug, + year = {2019}, + keywords = {Edge tokamak plasma, Fluid modeling, Transport}, + pages = {100685}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7JF7GXGF\\S2352179118302461.html:text/html}, } -@article{shah_spatially_2020, - title = {Spatially dependent kinetics of helium in tungsten under fusion conditions}, - volume = {535}, +@article{juslin_molecular_2013, + series = {Proceedings of the 20th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion} {Devices}}, + title = {Molecular dynamics simulation of the effect of sub-surface helium bubbles on hydrogen retention in tungsten}, + volume = {438}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311519306622}, - doi = {10.1016/j.jnucmat.2020.152104}, - abstract = {Tungsten is the prime candidate material for divertor applications in future nuclear reactors (e.g. ITER and DEMO). In the present work, a spatially dependent cluster dynamics model is developed to investigate and understand the microstructure evolution of tungsten under low energy helium implantation and neutron irradiation varying over bulk length scales of millimetres and irradiation time scales of hours. The diffusion of helium, helium clusters and their trapping at neutron induced defects is simulated along the tungsten monoblock depth. The temperature gradient resulting from a steady state heat load of 10 MWm−2 along the monoblock depth is considered and its influence on the evolution of defects is discussed. The trapping of helium at vacancies and the associated formation of helium-vacancy clusters is found to be pronounced in the sub-surface layers. A significant influence of helium detrapping from grain boundaries and dislocations, along with its resolution from clusters, on the helium diffusion length scales is observed. Additionally, the effect of helium cluster mobility is investigated and overall lower retention in the monoblock bulk is observed through significant release of helium at the surface.}, + url = {https://www.sciencedirect.com/science/article/pii/S002231151300278X}, + doi = {10.1016/j.jnucmat.2013.01.270}, + abstract = {Nanometer-sized bubbles in tungsten containing various concentrations of helium and/or hydrogen gas were studied using molecular dynamics simulations. Bubbles of different sizes and compositions were relaxed and evolved at temperatures from 300K to 2100K. Helium atoms are evenly distributed inside the bubble at all temperatures, while the hydrogen tends to diffuse to the bubble periphery. In all cases a large amount of hydrogen is bound within the first 1–2 layers of the tungsten matrix surrounding the bubble, though clear dependencies on temperature and bubble composition were found.}, language = {en}, - urldate = {2020-07-22}, + urldate = {2021-09-06}, journal = {Journal of Nuclear Materials}, - author = {Shah, V. and van Dommelen, J. A. W. and Geers, M. G. D.}, + author = {Juslin, N. and Wirth, B. D.}, month = jul, - year = {2020}, - keywords = {Cluster dynamics, Defect diffusion and accumulation, Helium implantation, Helium resolution, Neutron irradiation, Tungsten monoblock}, - pages = {152104}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PP6CQ23Y\\Shah et al. - 2020 - Spatially dependent kinetics of helium in tungsten.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\56S9H546\\S0022311519306622.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A8ABU89V\\Shah et al. - 2020 - Spatially dependent kinetics of helium in tungsten.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BS4AFSER\\S0022311519306622.html:text/html}, + year = {2013}, + pages = {S1221--S1223}, + annote = {H is on the edge of the bubble}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TRUWS9E3\\S002231151300278X.html:text/html}, } -@article{pecovnik_new_2020, - title = {New rate equation model to describe the stabilization of displacement damage by hydrogen atoms during ion irradiation in tungsten}, - volume = {60}, +@misc{delaporte-mathurin_irfmdivhretention_2021, + title = {{IRFM}/{divHretention} source code {Github} repository https://github.com/{IRFM}/{divHretention}}, + copyright = {MIT}, + url = {https://github.com/IRFM/divHretention}, + abstract = {Tool to estimate H retention in tokamak divertors}, + urldate = {2021-06-17}, + publisher = {Institute for Magnetic Fusion Research}, + author = {Delaporte-Mathurin, Rémi and Dark, James and Yang, Hao and Hodille, E. A.}, + month = jun, + year = {2021}, + note = {original-date: 2021-02-02T15:25:50Z}, +} + +@article{delaporte-mathurin_influence_2021-1, + title = {Influence of interface conditions on hydrogen transport studies}, + volume = {61}, + copyright = {All rights reserved}, issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Fab680f}, - doi = {10.1088/1741-4326/ab680f}, - abstract = {The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) during high-energy W-ion irradiation is investigated. For this purpose, we have performed modelling of experimental results where W was sequentially or simultaneously irradiated by 10.8 MeV W ions and exposed to 300 eV D ions. A novel displacement damage creation and stabilization model was newly developed and introduced into the MHIMS-Reservoir (migration of hydrogen isotopes in materials) code. It employs macroscopic rate equations (MREs) for solving the evolution of solute and trapped D concentrations in the material. The new displacement damage creation and stabilization model is based on spontaneous recombination of Frenkel pairs and stabilization of defects that are occupied by D atoms. By using the new model, we could successfully replicate the measured D depth profiles and D thermal desorption data, where a higher defect concentration was observed when D was present during W irradiation as compared to when no D was present. For this we utilized parameters, which include the number of distinct defect types, the de-trapping energies of their fill-levels, their saturation concentrations and their probability for stabilization if they contain a D during the W-ion irradiation. To successfully replicate the experimental results three distinct defect types were needed with several fill-levels. By comparing the de-trapping energies of the defect fill-levels with data available from the literature, the defect types were identified as single-vacancies, small vacancy clusters and large vacancy clusters. The effect of D presence was found to be largest in single vacancies as its concentration increased by about a factor of three, while the concentration of small vacancy clusters increased by about a factor of two. Large vacancy clusters were found to be largely unaffected as they showed very little increase in concentration when D was present.}, + url = {http://iopscience.iop.org/article/10.1088/1741-4326/abd95f}, + doi = {10.1088/1741-4326/abd95f}, + abstract = {This work investigates the influence of hydrogen chemical potential continuity across solid material interfaces. The implementation of the mathematical model in FESTIM is verified using the Method of Exact Solutions (MES) and the Method of Manufactured Solutions (MMS) in 1D, 2D, with complex material properties and inhomogeneous temperature fields. A comparison test between FESTIM, TMAP7 and Abaqus codes is also performed and the codes show good agreement. The chemical potential continuity condition has an impact up to 40\% on the outgassing particle flux on {\textbackslash}SI4mm composite slabs (W/Cu and Cu/EUROFER) compared to mobile concentration continuity. A method for rapid identification of materials properties from outgassing flux measurements is given. The influence of chemical potential conservation on monoblock inventory is then studied. It is shown that, for the 1D and 2D ITER divertor monobolocks cases, discrepancies only start to appear after approximately {\textbackslash}SI5e6s of full power.}, language = {en}, number = {3}, - urldate = {2020-02-26}, + urldate = {2021-01-08}, journal = {Nuclear Fusion}, - author = {Pečovnik, M. and Hodille, E. A. and Schwarz-Selinger, T. and Grisolia, C. and Markelj, S.}, - month = feb, - year = {2020}, - pages = {036024}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YK24AEMX\\Pečovnik et al. - 2020 - New rate equation model to describe the stabilizat.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QGLUF76F\\ab680f.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DMW39L8F\\Pečovnik et al. - 2020 - New rate equation model to describe the stabilizat.pdf:application/pdf}, + author = {Delaporte-Mathurin, Rémi and Hodille, Etienne and Mougenot, Jonathan and Charles, Yann and Temmerman, Gregory De and Leblond, Floriane and Grisolia, Christian}, + year = {2021}, + pages = {036038}, + file = {Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:D\:\\Logiciels\\data_zotero\\storage\\DT8CVDFY\\Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:application/pdf;IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XWFPUHLX\\Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:application/pdf}, } -@article{hou_predictive_2019, - title = {Predictive model of hydrogen trapping and bubbling in nanovoids in bcc metals}, - volume = {18}, - copyright = {2019 The Author(s), under exclusive licence to Springer Nature Limited}, - issn = {1476-4660}, - url = {https://www.nature.com/articles/s41563-019-0422-4}, - doi = {10.1038/s41563-019-0422-4}, - abstract = {The interplay between hydrogen and nanovoids, despite long being recognized as a central factor in hydrogen-induced damage in structural materials, remains poorly understood. Here, focusing on tungsten as a model body-centred cubic system, we explicitly demonstrate sequential adsorption of hydrogen adatoms on Wigner–Seitz squares of nanovoids with distinct energy levels. Interaction between hydrogen adatoms on nanovoid surfaces is shown to be dominated by pairwise power-law repulsion. We establish a predictive model for quantitative determination of the configurations and energetics of hydrogen adatoms in nanovoids. This model, combined with the equation of states of hydrogen gas, enables the prediction of hydrogen molecule formation in nanovoids. Multiscale simulations, performed based on our model, show good agreement with recent thermal desorption experiments. This work clarifies fundamental physics and provides a full-scale predictive model for hydrogen trapping and bubbling in nanovoids, offering long-sought mechanistic insights that are crucial for understanding hydrogen-induced damage in structural materials.}, +@article{khan_walldyn_2019, + title = {{WallDYN} simulations of material migration and fuel retention in {ITER} low power {H} plasmas and high power neon-seeded {DT} plasmas}, + volume = {20}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179119300134}, + doi = {10.1016/j.nme.2019.100674}, + abstract = {Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne impurity concentration are considered, representing high recycling and partially detached divertor solutions. The 2D SOLPS numerical grid does not extend all the way to the wall surfaces so that an extrapolation of the plasma background is required and is performed using a second simulation stage in which the far scrape-off layer (SOL) region is numerically gridded and plasma transport solved on the extended grid using the OSM (a 1D simplified Braginski code) approach [1]. The plasma conditions chosen for this far SOL region strongly influence the results. The hydrogenic flux is calculated from the electronic density and ion flow, the latter of which has an assumed distribution. Depending on the main-SOL plasma flow parameters and far-SOL density, fuel retention is driven by deposition on the first wall (when parallel flow through the main-SOL is switched off), or by deposition on the divertor (parallel flow through the main-SOL is switched on). When retention is dominated by deposition on the first wall, there is slightly more retention in the partially detached case compared to a high recycling scenario. In the low power cases, there is insignificant deposition and fuel retention.}, language = {en}, - number = {8}, - urldate = {2020-10-16}, - journal = {Nature Materials}, - author = {Hou, Jie and Kong, Xiang-Shan and Wu, Xuebang and Song, Jun and Liu, C. S.}, + urldate = {2020-09-16}, + journal = {Nuclear Materials and Energy}, + author = {Khan, A. and De Temmerman, G. and Lisgo, S. W. and Bonnin, X. and Anand, H. and Miller, M. A. and Pitts, R. A. and Schmid, K. and Kukushkin, A. S.}, month = aug, year = {2019}, - pages = {833--839}, - file = {Hou et al. - 2019 - Predictive model of hydrogen trapping and bubbling.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H9W727LI\\Hou et al. - 2019 - Predictive model of hydrogen trapping and bubbling.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\P3PGJKPX\\s41563-019-0422-4.html:text/html}, -} - -@article{hindmarch_odepack_1982, - title = {{ODEPACK}, {A} {Systematized} {Collection} of {ODE} {Solvers}}, - journal = {Scientific Computing}, - author = {Hindmarch, Alan C.}, - year = {1982}, - pages = {55--64}, - file = {Hindmarch - 1982 - ODEPACK, A Systematized Collection of ODE Solvers.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NCWC4WSN\\Hindmarch - 1982 - ODEPACK, A Systematized Collection of ODE Solvers.pdf:application/pdf}, -} - -@article{perrault_safety_2016, - series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, - title = {Safety issues to be taken into account in designing future nuclear fusion facilities}, - volume = {109-111}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379615302994}, - doi = {10.1016/j.fusengdes.2015.10.012}, - abstract = {For several years now, the French “Institut de Radioprotection et de Sûreté Nucléaire” has been carrying out expertise of ITER fusion facility safety files at the request of the French “Autorité de Sûreté Nucléaire”. As part of the lengthy process which should lead to mastering nuclear fusion, different fusion facility projects are currently under study throughout the world to be ready to continue building on the work which will take place in the ITER facility. On the basis of the experience acquired during the ITER safety expertise, the IRSN has carried out a preliminary study of the safety issues which seem necessary to take into account right from the earliest design phase of these DEMO facilities. The issues studied have included the decay heat removal, exposure to ionizing radiation, potential accidents, and effluent releases and waste. The study shows that it will be important to give priority to the following actions, given that their results would have a major influence on the design: assess if decay heat removal is a safety function, re-study the accidents considered in the context of the ITER project and identify those specific to DEMO, and optimize each of the main routes for gaseous tritium releases.}, - language = {en}, - urldate = {2020-10-14}, - journal = {Fusion Engineering and Design}, - author = {Perrault, Didier}, - month = nov, - year = {2016}, - keywords = {Tritium, Accident, Decay heat, DEMO, Effluents, safety, Safety}, - pages = {1733--1738}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\M6HGGM39\\Perrault - 2016 - Safety issues to be taken into account in designin.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NPYIL4M9\\S0920379615302994.html:text/html}, + pages = {100674}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DCZZSUYD\\Khan et al. - 2019 - WallDYN simulations of material migration and fuel.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\UI42XHNN\\S2352179119300134.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GTDSLUDM\\S2352179119300134.html:text/html}, } -@incollection{kirchheim_25_2014, - address = {Oxford}, - title = {25 - {Hydrogen} in {Metals}}, - isbn = {978-0-444-53770-6}, - url = {http://www.sciencedirect.com/science/article/pii/B9780444537706000253}, - abstract = {Hydrogen in metals attracts interest from scientists since many decades. Most of the interesting properties are related to the small size of hydrogen: its interstitial diffusion accompanied by quantum mechanical tunnel transport results in an extraordinary high mobility of hydrogen atoms in materials. For metals, H diffusivity may reach values as known for ions in aqueous solutions. Thus, thermodynamic equilibrium is reached within comparably short times even at room temperature. Therefore, metal–hydrogen systems are often used as model systems to study physical or chemical properties and their change with concentration (see, for example Oates and Flanagan, 1981, 1981a or Pundt and Kirchheim (2006)). In 1937, Lacher (1937) already used Pd–H (Flanagan and Oates, 1981, 1991) to study solute–solute interactions and interpreted it in the framework of a quasi-chemical approach (Lacher, 1937). The quantum mechanical tunneling as a diffusion mechanism also for atoms in solids was first discovered and discussed for hydrogen tunneling in metals (Flynn and Stoneham, 1970; Völk and Alefeld, 1975; Birnbaum and Flynn, 1976). Völk and Alefeld (1978), Zabel and Peisl (1979, 1980), and Steyrer and Peisl (1986) studied hydrogen density modulations that are related to the sample geometry; and Zabel and his colleagues, as published by Miceli et al. (1985), Uher et al. (1987), Song et al. (1996, 2000), and Uher et al. (1987), firstly used metal–hydrogen systems to study the behavior of systems with reduced dimensions and modulated hydrogen affinity. Kirchheim (1988) and colleagues extensively studied metal–hydrogen systems as representative for solute/solvent systems. The high mobility of hydrogen further allows studying the impact of defects that usually annihilate at elevated temperatures, see Gottstein (2001). It was, therefore, suggested to use hydrogen as a probe for defects (Cahn, 1990; Flanagan et al., 2001a, 2001b; Kirchheim, 2004) and perform site energy spectroscopy by gradually increasing the hydrogen chemical potential.}, +@article{ezell_neutron_2021, + title = {Neutron irradiation of alloy {N} and {316L} stainless steel in contact with a molten chloride salt}, + volume = {53}, + issn = {1738-5733}, + url = {https://www.sciencedirect.com/science/article/pii/S1738573320308044}, + doi = {10.1016/j.net.2020.07.042}, + abstract = {Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. +Index Terms +Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.}, language = {en}, - urldate = {2020-10-09}, - booktitle = {Physical {Metallurgy} ({Fifth} {Edition})}, - publisher = {Elsevier}, - author = {Kirchheim, R. and Pundt, A.}, - editor = {Laughlin, David E. and Hono, Kazuhiro}, - month = jan, - year = {2014}, - doi = {10.1016/B978-0-444-53770-6.00025-3}, - keywords = {Accumulative roll bonding (ARB), Amorphous phases, Atomic mobility, Chemical vapor deposition (CVD), Electrochemical deposition (ED), Electromotoric force, Equal channel angular pressing (ECAP), Geometric phase analysis (GPA), Grain boundary, High pressure torsion (HPT), High resolution transmission electron microscopy (HRTEM), Inert gas condensation (IGC), Metallic Materials, Nanocrystalline materials, Nanocrystalline microstructures, Nanostructured materials, Obtain graded nanostructures, Physical vapor deposition (PVD), Plastic deformation, Severe plastic deformation (SPD), Sputter deposition, Synthesis options, Thin film shess}, - pages = {2597--2705}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YC8VQ7T5\\B9780444537706000253.html:text/html}, + number = {3}, + urldate = {2021-05-05}, + journal = {Nuclear Engineering and Technology}, + author = {Ezell, N. Dianne Bull and Raiman, Stephen S. and Kurley, J. Matt and McDuffee, Joel}, + month = mar, + year = {2021}, + keywords = {Corrosion, High-temperature experiment, Irradiation, Molten Salt Reactor}, + pages = {920--926}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XCBP4Y5S\\Ezell et al. - 2021 - Neutron irradiation of alloy N and 316L stainless .pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DJRL985G\\Ezell et al. - 2021 - Neutron irradiation of alloy N and 316L stainless .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KF3NNBDV\\S1738573320308044.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\WTQTNJPG\\S1738573320308044.html:text/html}, } -@article{krom_hydrogen_2000, - title = {Hydrogen trapping models in steel}, - volume = {31}, - issn = {1543-1916}, - url = {https://doi.org/10.1007/s11663-000-0032-0}, - doi = {10.1007/s11663-000-0032-0}, - abstract = {This article describes the role of hydrogen trapping in steel. Trapping increases the solubility of hydrogen and decreases the diffusivity. Traps are characterized by their nature, i.e., reversible or irreversible, saturable or unsaturable. A dislocation core is a saturable, reversible trap, while voids and crack are unsaturable, reversible traps. A trap model based on saturable, reversible traps is developed, which is slightly different from the trap model of McNabb and Foster. In equilibrium, the trap model corresponds to Oriani’s trap model. Kumnick and Johnson found experimentally that the trap density increases as the plastic strain increases. Using their trap data, it is shown that equilibrium between hydrogen in lattice sites and trap sites can be assumed when strain rates are used as in standard tensile tests.}, - language = {en}, - number = {6}, - urldate = {2020-10-09}, - journal = {Metallurgical and Materials Transactions B}, - author = {Krom, Alfons H. M. and Bakker, Ad}, +@article{1986STIN...8729795K, + title = {Finite-element reentry heat-transfer analysis of space shuttle {Orbiter}}, + volume = {87}, + url = {https://ui.adsabs.harvard.edu/abs/1986STIN...8729795K}, + abstract = {A structural performance and resizing (SPAR) finite-element thermal analysis computer program was used in the heat-transfer analysis of the space shuttle orbiter subjected to reentry aerodynamic heating. Three wing cross sections and one midfuselage cross section were selected for the thermal analysis. The predicted thermal protection system temperatures were found to agree well with flight-measured temperatures. The calculated aluminum structural temperatures also agreed reasonably well with the flight data from reentry to touchdown. The effects of internal radiation and of internal convection were found to be significant. The SPAR finite-element solutions agreed reasonably well with those obtained from the conventional finite-difference method.}, + urldate = {2021-08-19}, + journal = {NASA STI/Recon Technical Report N}, + author = {Ko, William L. and Quinn, Robert D. and Gong, Leslie}, month = dec, - year = {2000}, - pages = {1475--1482}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3CM9W6NN\\Krom et Bakker - 2000 - Hydrogen trapping models in steel.pdf:application/pdf}, -} - -@book{smith_abaqusstandard_2009, - title = {{ABAQUS}/{Standard} {User}'s {Manual}, {Version} 6.9}, - url = {https://www.research.manchester.ac.uk/portal/en/publications/abaqusstandard-users-manual-version-69(0b112d0e-5eba-4b7f-9768-cfe1d818872e).html}, - language = {English}, - urldate = {2020-10-09}, - author = {Smith, Michael}, - year = {2009}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\B7Q393PQ\\abaqusstandard-users-manual-version-69(0b112d0e-5eba-4b7f-9768-cfe1d818872e).html:text/html}, -} - -@article{aiello_hydrogen_2002, - title = {Hydrogen {Isotopes} {Permeability} in {Eurofer} 97 {Martensitic} {Steel}}, - volume = {41}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST41-872}, - doi = {10.13182/FST41-872}, - abstract = {In considering structural materials for fusion reactors a detailed understanding of the transport parameters and solubility of hydrogen and its isotopes is an important issue which deal with safety and blanket performance aspects.The experimental activities were focused on the determination of hydrogen/deuterium transport parameters through Eurofer 97 in the temperature range 423+723K using a time dependant permeation technique The hydrogen permeation and diffusivity at room temperature and density of trapping sites were also evaluated using Devanathan’s technique.Hydrogen / deuterium permeation experiments on Eurofer 97 showed a non-negligible decrease in permeability with respect to other fusion oriented martensitic steels, even if it remains about one order of magnitude higher compared with that of austenitic AISI 316L steel.}, - number = {3P2}, - urldate = {2020-10-09}, - journal = {Fusion Science and Technology}, - author = {Aiello, A. and Ricapito, I. and Benamati, G. and Valentini, R.}, - month = may, - year = {2002}, - pages = {872--876}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IAJK39YH\\FST41-872.html:text/html}, + year = {1986}, + note = {ADS Bibcode: 1986STIN...8729795K}, + keywords = {Aerodynamic Heating, Aircraft Structures, Aluminum, Convection, Cross Sections, Finite Element Method, Fluid Mechanics and Heat Transfer, Heat Transfer Coefficients, Reentry Shielding, Space Shuttle Orbiters, Space Transportation System, Surface Temperature, Thermal Analysis, Thermal Protection, Wings}, + pages = {29795}, } -@article{benannoune_numerical_2018, - title = {Numerical simulation of the transient hydrogen trapping process using an analytical approximation of the {McNabb} and {Foster} equation}, - volume = {43}, - issn = {0360-3199}, - url = {http://www.sciencedirect.com/science/article/pii/S0360319918310115}, - doi = {10.1016/j.ijhydene.2018.03.179}, - abstract = {In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures, an analytical solution for the differential equation of trapping kinetics is proposed, as a generalization of the Oriani's equilibrium relationship. This solution has been implemented in the Abaqus finite element software, and validated by comparison with the one-dimensional kinetic MRE Hydrogen Isotope Inventory Processes Code (HIIPC). Last, the results of an application on a 3D structure are presented.}, +@article{hecht_new_2012, + title = {New development in freefem++}, + volume = {20}, + issn = {1569-3953, 1570-2820}, + url = {https://www.degruyter.com/document/doi/10.1515/jnum-2012-0013/html}, + doi = {10.1515/jnum-2012-0013}, + abstract = {This is a short presentation to the capability of the freefem++ software, in section 1, we recall most of the characteristics of the software, In section 2, we recall how to to build a weak form form of an partial differential equation (PDE) from the strong form of the PDE. In three last sections, we present different problem, tools to illustrated the software. First we do mesh adaptation problem in two and three dimension,, secondly, we solve numerically a Phase change with Natural Convection, and the finally to show the HPC possibility we show a Schwarz Domain Decomposition problem on parallel computer.}, language = {en}, - number = {18}, - urldate = {2020-09-30}, - journal = {International Journal of Hydrogen Energy}, - author = {Benannoune, Sofiane and Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, - month = may, - year = {2018}, - keywords = {Abaqus, Finite elements calculations, Hydrogen diffusion, Kinetic trapping, MRE, User subroutine}, - pages = {9083--9093}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZQFQ7R7S\\S0360319918310115.html:text/html}, + number = {3-4}, + urldate = {2021-07-14}, + journal = {Journal of Numerical Mathematics}, + author = {Hecht, F.}, + month = jan, + year = {2012}, + file = {Hecht - 2012 - New development in freefem++.pdf:D\:\\Logiciels\\data_zotero\\storage\\DLBP27YD\\Hecht - 2012 - New development in freefem++.pdf:application/pdf}, } -@article{oh_coupled_2010, - title = {Coupled {Analysis} of {Hydrogen} {Transport} using {ABAQUS}}, - volume = {4}, - doi = {10.1299/jmmp.4.908}, - abstract = {This paper describes two user subroutines developed within ABAQUS to simulate coupled hydrogen transport equations. Developed user subroutines incorporate two key features in coupled hydrogen transport equations, such as the hydrostatic stress and plastic strain effects on hydrogen transport, and hydrogen-induced dilatational deformation rate. To validate developed subroutines, present simulation results are compared with published results, showing good agreements for all cases considered.}, - number = {7}, - journal = {Journal of Solid Mechanics and Materials Engineering}, - author = {Oh, Chang-Sik and Kim, Yun-Jae and Yoon, Kee-Bong}, - year = {2010}, - keywords = {ABAQUS, Hydrogen Transport Simulation}, - pages = {908--917}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\54AAJFQY\\Oh et al. - 2010 - Coupled Analysis of Hydrogen Transport using ABAQU.pdf:application/pdf;J-Stage - Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\82Z5UY8I\\_article.html:text/html}, +@article{arndt_dealii_2021, + series = {Development and {Application} of {Open}-source {Software} for {Problems} with {Numerical} {PDEs}}, + title = {The deal.{II} finite element library: {Design}, features, and insights}, + volume = {81}, + issn = {0898-1221}, + shorttitle = {The deal.{II} finite element library}, + url = {https://www.sciencedirect.com/science/article/pii/S0898122120300894}, + doi = {10.1016/j.camwa.2020.02.022}, + abstract = {deal.II is a state-of-the-art finite element library focused on generality, dimension-independent programming, parallelism, and extensibility. Herein, we outline its primary design considerations and its sophisticated features such as distributed meshes, hp-adaptivity, support for complex geometries, and matrix-free algorithms. But deal.II is more than just a software library: It is also a diverse and worldwide community of developers and users, as well as an educational platform. We therefore also discuss some of the technical and social challenges and lessons learned in running a large community software project over the course of two decades.}, + language = {en}, + urldate = {2021-07-14}, + journal = {Computers \& Mathematics with Applications}, + author = {Arndt, Daniel and Bangerth, Wolfgang and Davydov, Denis and Heister, Timo and Heltai, Luca and Kronbichler, Martin and Maier, Matthias and Pelteret, Jean-Paul and Turcksin, Bruno and Wells, David}, + month = jan, + year = {2021}, + keywords = {Finite elements, Mathematical software, Scientific computing, Software design}, + pages = {407--422}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XUMNAEXR\\Arndt et al. - 2021 - The deal.II finite element library Design, featur.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\FB5JQUWY\\S0898122120300894.html:text/html}, } -@article{vasikaran_implementation_2020, - title = {Implementation of a reaction-diffusion process in the {Abaqus} finite element software}, - volume = {21}, - copyright = {© E. Vasikaran et al., published by EDP Sciences 2020}, - issn = {2257-7777, 2257-7750}, - url = {https://www.mechanics-industry.org/articles/meca/abs/2020/05/mi190305/mi190305.html}, - doi = {10.1051/meca/2020010}, - abstract = {To increase the Abaqus software capabilities, we propose a strategy to force the software to activate hidden degrees of freedom and to include extra coupled phenomena. As an illustration, we apply this approach to the simulation of a reaction diffusion process, the Gray-Scott model, which exhibits very complex patterns. Several setups have been considered and compared with available results to analyze the abilities of our strategy and to allow the inclusion of complex phenomena in Abaqus.}, +@article{permann_moose_2020, + title = {{MOOSE}: {Enabling} massively parallel multiphysics simulation}, + volume = {11}, + issn = {2352-7110}, + shorttitle = {{MOOSE}}, + url = {https://www.sciencedirect.com/science/article/pii/S2352711019302973}, + doi = {10.1016/j.softx.2020.100430}, + abstract = {Harnessing modern parallel computing resources to achieve complex multiphysics simulations is a daunting task. The Multiphysics Object Oriented Simulation Environment (MOOSE) aims to enable such development by providing simplified interfaces for specification of partial differential equations, boundary conditions, material properties, and all aspects of a simulation without the need to consider the parallel, adaptive, nonlinear, finite element solve that is handled internally. Through the use of interfaces and inheritance, each portion of a simulation becomes reusable and composable in a manner that allows disparate research groups to share code and create an ecosystem of growing capability that lowers the barrier for the creation of multiphysics simulation codes. Included within the framework is a unique capability for building multiscale, multiphysics simulations through simultaneous execution of multiple sub-applications with data transfers between the scales. Other capabilities include automatic differentiation, scaling to a large number of processors, hybrid parallelism, and mesh adaptivity. To date, MOOSE-based applications have been created in areas of science and engineering such as nuclear physics, geothermal science, magneto-hydrodynamics, seismic events, compressible and incompressible fluid flow, microstructure evolution, and advanced manufacturing processes.}, language = {en}, - number = {5}, - urldate = {2020-09-30}, - journal = {Mechanics \& Industry}, - author = {Vasikaran, Elisabeth and Charles, Yann and Gilormini, Pierre}, + urldate = {2021-07-14}, + journal = {SoftwareX}, + author = {Permann, Cody J. and Gaston, Derek R. and Andrš, David and Carlsen, Robert W. and Kong, Fande and Lindsay, Alexander D. and Miller, Jason M. and Peterson, John W. and Slaughter, Andrew E. and Stogner, Roy H. and Martineau, Richard C.}, + month = jan, year = {2020}, - note = {Number: 5 -Publisher: EDP Sciences}, - pages = {508}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZRA6BK8K\\mi190305.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IG3TQ86U\\Vasikaran et al. - 2020 - Implementation of a reaction-diffusion process in .pdf:application/pdf}, + keywords = {Finite-element, Framework, Multiphysics, Multiscale, Parallel}, + pages = {100430}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FY3A5SV2\\Permann et al. - 2020 - MOOSE Enabling massively parallel multiphysics si.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\UEBTI36N\\S2352711019302973.html:text/html}, } -@article{marchi_permeability_2007, - title = {Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures}, - volume = {32}, - issn = {0360-3199}, - url = {http://www.sciencedirect.com/science/article/pii/S0360319906001753}, - doi = {10.1016/j.ijhydene.2006.05.008}, - abstract = {In this report, we provide a framework for describing the permeability, solubility and diffusivity of hydrogen and its isotopes in austenitic stainless steels at temperatures and high gas pressures of engineering interest for hydrogen storage and distribution infrastructure. We demonstrate the importance of using the real gas behavior for modeling permeation and dissolution of hydrogen under these conditions. A simple one-parameter equation of state (the Abel–Noble equation of state) is shown to capture the real gas behavior of hydrogen and its isotopes for pressures less than 200MPa and temperatures between 223 and 423K. We use the literature on hydrogen transport in austenitic stainless steels to provide general guidance on and clarification of test procedures, and to provide recommendations for appropriate permeability, diffusivity and solubility relationships for austenitic stainless steels. Hydrogen precharging and concentration measurements for a variety of austenitic stainless steels are described and used to generate more accurate solubility and diffusivity relationships.}, - language = {en}, - number = {1}, - urldate = {2020-09-21}, - journal = {International Journal of Hydrogen Energy}, - author = {Marchi, C. San and Somerday, B. P. and Robinson, S. L.}, - month = jan, - year = {2007}, - keywords = {Diffusivity, High-pressure hydrogen gas, Hydrogen isotopes, Permeability, Solubility}, - pages = {100--116}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UHUN39Y2\\Marchi et al. - 2007 - Permeability, solubility and diffusivity of hydrog.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZV87U7TW\\S0360319906001753.html:text/html}, +@misc{kolev_tzanio_modular_2010, + title = {Modular {Finite} {Element} {Methods} ({MFEM})}, + url = {https://www.osti.gov/doecode/biblio/35738}, + abstract = {MFEM is a modular parallel C++ library for finite element methods. Its goal is to enable high-performance scalable finite element discretization research and application development on a wide variety of platforms, ranging from laptops to supercomputers.}, + urldate = {2021-07-14}, + publisher = {Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)}, + author = {Kolev, Tzanio and Dobrev, Veselin}, + year = {2010}, + doi = {10.11578/DC.20171025.1248}, + note = {Language: en}, } -@techreport{longhurst_tmap7_2008, - title = {{TMAP7} {User} {Manual}}, - url = {https://www.osti.gov/biblio/952013-tmap7-user-manual}, - abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information}, - language = {English}, - number = {INEEL/EXT-04-02352}, - urldate = {2020-09-20}, - institution = {Idaho National Laboratory (INL)}, - author = {Longhurst, Glen R.}, - month = dec, - year = {2008}, - doi = {10.2172/952013}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HE9NG682\\952013-tmap7-user-manual.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GV8WB3C7\\Longhurst - 2008 - TMAP7 User Manual.pdf:application/pdf}, +@article{harris_array_2020, + title = {Array programming with {NumPy}}, + volume = {585}, + copyright = {2020 The Author(s)}, + issn = {1476-4687}, + url = {https://www.nature.com/articles/s41586-020-2649-2}, + doi = {10.1038/s41586-020-2649-2}, + abstract = {Array programming provides a powerful, compact and expressive syntax for accessing, manipulating and operating on data in vectors, matrices and higher-dimensional arrays. NumPy is the primary array programming library for the Python language. It has an essential role in research analysis pipelines in fields as diverse as physics, chemistry, astronomy, geoscience, biology, psychology, materials science, engineering, finance and economics. For example, in astronomy, NumPy was an important part of the software stack used in the discovery of gravitational waves1 and in the first imaging of a black hole2. Here we review how a few fundamental array concepts lead to a simple and powerful programming paradigm for organizing, exploring and analysing scientific data. NumPy is the foundation upon which the scientific Python ecosystem is constructed. It is so pervasive that several projects, targeting audiences with specialized needs, have developed their own NumPy-like interfaces and array objects. Owing to its central position in the ecosystem, NumPy increasingly acts as an interoperability layer between such array computation libraries and, together with its application programming interface (API), provides a flexible framework to support the next decade of scientific and industrial analysis.}, + language = {en}, + number = {7825}, + urldate = {2021-07-13}, + journal = {Nature}, + author = {Harris, Charles R. and Millman, K. Jarrod and van der Walt, Stéfan J. and Gommers, Ralf and Virtanen, Pauli and Cournapeau, David and Wieser, Eric and Taylor, Julian and Berg, Sebastian and Smith, Nathaniel J. and Kern, Robert and Picus, Matti and Hoyer, Stephan and van Kerkwijk, Marten H. and Brett, Matthew and Haldane, Allan and del Río, Jaime Fernández and Wiebe, Mark and Peterson, Pearu and Gérard-Marchant, Pierre and Sheppard, Kevin and Reddy, Tyler and Weckesser, Warren and Abbasi, Hameer and Gohlke, Christoph and Oliphant, Travis E.}, + month = sep, + year = {2020}, + note = {Bandiera\_abtest: a +Cc\_license\_type: cc\_by +Cg\_type: Nature Research Journals +Number: 7825 +Primary\_atype: Reviews +Publisher: Nature Publishing Group +Subject\_term: Computational neuroscience;Computational science;Computer science;Software;Solar physics +Subject\_term\_id: computational-neuroscience;computational-science;computer-science;software;solar-physics}, + pages = {357--362}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4RM3MURH\\Harris et al. - 2020 - Array programming with NumPy.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YD8RZXXI\\s41586-020-2649-2.html:text/html}, } -@book{reiter_compilation_1996, - title = {A compilation of tritium : {Material} interaction parameters in fusion reactor materials.}, - shorttitle = {A compilation of tritium}, - abstract = {Details of the publication}, +@article{schindelin_fiji_2012, + title = {Fiji: an open-source platform for biological-image analysis}, + volume = {9}, + copyright = {2012 Nature Publishing Group, a division of Macmillan Publishers Limited. All Rights Reserved.}, + issn = {1548-7105}, + shorttitle = {Fiji}, + url = {https://www.nature.com/articles/nmeth.2019}, + doi = {10.1038/nmeth.2019}, + abstract = {Presented is an overview of the image-analysis software platform Fiji, a distribution of ImageJ that updates the underlying ImageJ architecture and adds modern software design elements to expand the capabilities of the platform and facilitate collaboration between biologists and computer scientists.}, language = {en}, - urldate = {2020-04-16}, - publisher = {Publications Office of the European Union}, - author = {Reiter, F. and Forcey, K. S. and Gervasini, G.}, + number = {7}, + urldate = {2021-07-13}, + journal = {Nature Methods}, + author = {Schindelin, Johannes and Arganda-Carreras, Ignacio and Frise, Erwin and Kaynig, Verena and Longair, Mark and Pietzsch, Tobias and Preibisch, Stephan and Rueden, Curtis and Saalfeld, Stephan and Schmid, Benjamin and Tinevez, Jean-Yves and White, Daniel James and Hartenstein, Volker and Eliceiri, Kevin and Tomancak, Pavel and Cardona, Albert}, month = jul, - year = {1996}, - file = {Union - 1996 - A compilation of tritium Material interaction pa.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\B3DLFNWI\\Union - 1996 - A compilation of tritium Material interaction pa.pdf:application/pdf}, + year = {2012}, + note = {Bandiera\_abtest: a +Cg\_type: Nature Research Journals +Number: 7 +Primary\_atype: Reviews +Publisher: Nature Publishing Group +Subject\_term: Imaging;Software +Subject\_term\_id: imaging;software}, + pages = {676--682}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CSF5JV63\\nmeth.html:text/html;Version acceptée:D\:\\Logiciels\\data_zotero\\storage\\2B3DHAN9\\Schindelin et al. - 2012 - Fiji an open-source platform for biological-image.pdf:application/pdf}, } -@article{pacher_impurity_2015, - title = {Impurity seeding in {ITER} {DT} plasmas in a carbon-free environment}, - volume = {463}, - issn = {0022-3115}, - url = {http://adsabs.harvard.edu/abs/2015JNuM..463..591P}, - doi = {10.1016/j.jnucmat.2014.11.104}, - abstract = {Impurity seeding has been studied for a carbon-free divertor configuration in ITER using edge/divertor SOLPS code simulations. For high power DT operation, simulations have been performed for varying throughput, power, pumping speed, impurity seeding concentration and species and the results have been parameterised. With these scalings as boundary conditions, core simulations have determined the operating window for carbon-free, impurity-seeded operation.}, - urldate = {2020-09-16}, - journal = {Journal of Nuclear Materials}, - author = {Pacher, H. D. and Kukushkin, A. S. and Pacher, G. W. and Kotov, V. and Pitts, R. A. and Reiter, D.}, - month = aug, - year = {2015}, - pages = {591--595}, +@misc{delaporte-mathurin_divhretention_nodate, + title = {{divHretention}: {Tool} to estimate {H} retention in tokamak divertors, v0.1.3 {PyPi} distribution}, + copyright = {MIT License}, + shorttitle = {{divHretention}}, + url = {https://pypi.org/project/divHretention/}, + urldate = {2021-06-18}, + author = {Delaporte-Mathurin, Remi}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4WKYK3W2\\divHretention.html:text/html}, } -@article{khan_walldyn_2019, - title = {{WallDYN} simulations of material migration and fuel retention in {ITER} low power {H} plasmas and high power neon-seeded {DT} plasmas}, - volume = {20}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179119300134}, - doi = {10.1016/j.nme.2019.100674}, - abstract = {Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne impurity concentration are considered, representing high recycling and partially detached divertor solutions. The 2D SOLPS numerical grid does not extend all the way to the wall surfaces so that an extrapolation of the plasma background is required and is performed using a second simulation stage in which the far scrape-off layer (SOL) region is numerically gridded and plasma transport solved on the extended grid using the OSM (a 1D simplified Braginski code) approach [1]. The plasma conditions chosen for this far SOL region strongly influence the results. The hydrogenic flux is calculated from the electronic density and ion flow, the latter of which has an assumed distribution. Depending on the main-SOL plasma flow parameters and far-SOL density, fuel retention is driven by deposition on the first wall (when parallel flow through the main-SOL is switched off), or by deposition on the divertor (parallel flow through the main-SOL is switched on). When retention is dominated by deposition on the first wall, there is slightly more retention in the partially detached case compared to a high recycling scenario. In the low power cases, there is insignificant deposition and fuel retention.}, +@article{spagnuolo_multi-physics_2019, + title = {A multi-physics integrated approach to breeding blanket modelling and design}, + volume = {143}, + issn = {09203796}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379619304648}, + doi = {10.1016/j.fusengdes.2019.03.131}, language = {en}, - urldate = {2020-09-16}, - journal = {Nuclear Materials and Energy}, - author = {Khan, A. and De Temmerman, G. and Lisgo, S. W. and Bonnin, X. and Anand, H. and Miller, M. A. and Pitts, R. A. and Schmid, K. and Kukushkin, A. S.}, - month = aug, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Spagnuolo, Gandolfo Alessandro and Chiovaro, Pierluigi and Di Maio, Pietro Alessandro and Favetti, Riccardo}, + month = jun, year = {2019}, - pages = {100674}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DCZZSUYD\\Khan et al. - 2019 - WallDYN simulations of material migration and fuel.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GTDSLUDM\\S2352179119300134.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UI42XHNN\\S2352179119300134.html:text/html}, + pages = {35--40}, + file = {Spagnuolo et al. - 2019 - A multi-physics integrated approach to breeding bl.pdf:D\:\\Logiciels\\data_zotero\\storage\\X9QTMGK2\\Spagnuolo et al. - 2019 - A multi-physics integrated approach to breeding bl.pdf:application/pdf}, } -@article{barrett_designs_2019, - title = {Designs and technologies for plasma-facing wall protection in {EU} {DEMO}}, - volume = {59}, +@article{urgorri_tritium_2017, + title = {Tritium transport modeling at system level for the {EUROfusion} dual coolant lithium-lead breeding blanket}, + volume = {57}, issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Fab085b}, - doi = {10.1088/1741-4326/ab085b}, - abstract = {The EU DEMO plasma is almost completely enveloped by large breeding blanket segments for tritium breeding and power extraction. Shaping of the blanket plasma-facing wall in 3D may prove to be essential, but this strategy alone is not sufficient to protect against anticipated transient plasma events. The high heat flux wall-limiter approach used in ITER is not thought to be viable in a tritium self-sufficient power reactor, and so in EU DEMO wall protection using discrete limiters is pursued. Two types of discrete limiter are described in this paper. One is an equatorial port limiter designed to handle the power during the plasma start-up phase, making use of water-cooled tungsten/CuCrZr monoblock technology. The second is the upper limiter, featuring a plasma-facing component designed specifically for extreme transient loading due to a vertical displacement event. The heat flux channelling and thermal barrier features of this design are shown to considerably reduce CuCrZr pipe temperature, and so reduce the likelihood of catastrophic failure. A preliminary neutronic calculation has shown that the impact of these discrete limiters on overall tritium breeding ratio is relatively low.}, + url = {https://doi.org/10.1088/1741-4326/aa7f9d}, + doi = {10.1088/1741-4326/aa7f9d}, + abstract = {The dual coolant lithium lead (DCLL) breeding blanket is one of the four breeder blanket concepts under consideration within the framework of EUROfusion consortium activities. The aim of this work is to develop a model that can dynamically track tritium concentrations and fluxes along each part of the DCLL blanket and the ancillary systems associated to it at any time. Because of tritium nature, the phenomena of diffusion, dissociation, recombination and solubilisation have been modeled in order to describe the interaction between the lead-lithium channels, the structural material, the flow channel inserts and the helium channels that are present in the breeding blanket. Results have been obtained for a pulsed generation scenario for DEMO. The tritium inventory in different parts of the blanket, the permeation rates from the breeder to the secondary coolant and the amount of tritium extracted from the lead-lithium loop have been computed. Results present an oscillating behavior around mean values. The obtained average permeation rate from the liquid metal to the helium is 1.66 mg while the mean tritium inventory in the whole system is 417 mg. Besides the reference case results, parametric studies of the lead-lithium mass flow rate, the tritium extraction efficiency and the tritium solubility in lead-lithium have been performed showing the reaction of the system to the variation of these parameters.}, language = {en}, - number = {5}, - urldate = {2020-09-15}, + number = {11}, + urldate = {2021-01-12}, journal = {Nuclear Fusion}, - author = {Barrett, T. R. and Chuilon, B. and Kovari, M. and Hernandez, D. Leon and Richiusa, M. L. and Adame, E. Rosa and Tivey, R. and Vizvary, Z. and Xue, Y. and Maviglia, F.}, - month = apr, - year = {2019}, - pages = {056019}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X7GDM7E9\\Barrett et al. - 2019 - Designs and technologies for plasma-facing wall pr.pdf:application/pdf}, + author = {Urgorri, F. R. and Moreno, C. and Carella, E. and Rapisarda, D. and Fernández-Berceruelo, I. and Palermo, I. and Ibarra, A.}, + month = aug, + year = {2017}, + note = {Publisher: IOP Publishing}, + pages = {116045}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\E7E993WC\\Urgorri et al. - 2017 - Tritium transport modeling at system level for the.pdf:application/pdf}, } -@article{salari_code_nodate, - title = {Code {Verification} by the {Method} of {Manufactured} {Solutions}}, - abstract = {A procedure for code Verification by the Method of Manufactured Solutions (MMS) is presented. Although the procedure requires a certain amount of creativity and skill, we show that MMS can be applied to a variety of engineering codes which numerically solve partial differential equations. This is illustrated by detailed examples from computational fluid dynamics. The strength of the MMS procedure is that it can identify any coding mistake that affects the order-of-accuracy of the numerical method. A set of examples which use a blind-test protocol demonstrates the kinds of coding mistakes that can (and cannot) be exposed via the MMS code Verification procedure. The principle advantage of the MMS procedure over traditional methods of code Verification is that code capabilities are tested in full generality. The procedure thus results in a high degree of confidence that all coding mistakes which prevent the equations from being solved correctly have been identified.}, +@article{li_development_2020, + title = {Development of tritium dynamic transport analysis tool for tritium breeding blanket system using {Modelica}}, + volume = {161}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620305718}, + doi = {10.1016/j.fusengdes.2020.112023}, + abstract = {Demonstration of the engineering feasibility of tritium breeding, including tritium generation, tritium extraction, tritium control and tritium safety is one of the main objectives of ITER Testing Blanket Module (TBM) Program. As one of TBM concepts, the tritium transport assessment of the China Helium Cooled Ceramic Breeder TBM and its ancillary systems (called test blanket system, TBS) is absolutely vital to understand and analyze the dynamic tritium behaviors in the system in detail according to the ITER operation scenario. Considering the requirements of the tritium transport analysis for the HCCB TBS, an integrated dynamic tritium transport analysis tool has been developed by the system simulation language “Modelica”. The multiple dynamic physics effects are considered in the tool, including the aspects impacting the tritium transport, simplified thermal-hydraulics considering only the linear loss and local loss in fluid, 1-d thermal conduction in solid, hydrogen isotope transport in fluid, 1-d tritium permeation in solid, tritium solution and recombination on solid surfaces, tritium desorption from ceramic breeder etc. A simplified model of the HCCB TBS is modeled to verify the functions and accuracy of this tool. The results, such as dynamic change of tritium concentration/partial pressure in fluids, dynamic change of tritium inventory in solids, tritium permeation fluxes etc., have been obtained, which are preliminary verified at various aspects by comparing with analytical and hand calculations.}, language = {en}, - author = {Salari, Kambiz and Knupp, Patrick}, - pages = {124}, - file = {Salari et Knupp - Code Verification by the Method of Manufactured Sol.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\AIP2VDC5\\Salari et Knupp - Code Verification by the Method of Manufactured Sol.pdf:application/pdf}, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Li, Ruyan and Wang, Xiaoyu and Zhang, Long and Wang, Jun}, + month = dec, + year = {2020}, + keywords = {Dynamic tritium transport, HCCB TBS, Modelica}, + pages = {112023}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MMBF3MLB\\Li et al. - 2020 - Development of tritium dynamic transport analysis .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GT6VJMZ2\\S0920379620305718.html:text/html}, } -@article{sun_modeling_2020, - title = {Modeling and simulation for surface helium effect on hydrogen isotopes diffusion and trapping/detrapping behavior in plasma facing materials}, - volume = {537}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311519315089}, - doi = {10.1016/j.jnucmat.2020.152227}, - abstract = {In this study, surface helium (He) effect on hydrogen isotopes diffusion and trapping/detrapping behavior was modelled and integrated into the HIDT simulation code. Effective dynamics properties of hydrogen in tungsten including diffusivity, solubility, recycling and diffusion barrier were considered to reflect the influence of He bubbles. Simulation results showed that total hydrogen retention was reduced with the existence of He bubbles near surface, which was consistent with the reported laboratory experimental results. It was found that the most significant influence came from the diffusion barrier induced by He bubbles. With increasing the barrier factor, total hydrogen retention changed from the tendency of decrease to increase. When the barrier factor was less than 0.3, hydrogen desorption from the implantation surface was dominant, while that from the backside surface became dominant when the barrier factor was greater than 0.4. In the meanwhile, more hydrogen accumulated beyond the He bubble layer was observed. These hydrogen atoms occupied not only in trapping sites, but also in lattice sites. Based on these findings, three desorption stages, namely surface desorption, major desorption and backside desorption, could characterize the TDS spectra with different mechanisms. In addition, our findings were further substantiated by the reported experimental data. This study provides a new perspective to reveal the surface He effect on hydrogen isotopes retention behavior in plasma facing materials.}, +@article{candido_integrated_2020, + title = {An integrated hydrogen isotopes transport model for the {TRIEX}-{II} facility}, + volume = {155}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620301332}, + doi = {10.1016/j.fusengdes.2020.111585}, + abstract = {At ENEA Brasimone Research Centre, Italy, a new experimental facility named TRIEX-II (Tritium Extraction) was designed and installed. Its aim is to characterize, in the range of operating conditions foreseen for the European Test Blanket System WCLL-TBS, several extraction technologies for hydrogen isotopes (Q2) solubilized in the flowing metallic LiPb alloy (15.7 at. \% Li). One of these technologies is the packed column, an example of Gas/Liquid Contactors (GLCs). This paper proposes a multiscale modelling tool, combining different scales through two computational tools. The extraction column mock-up is described by a component-detail level model, developed in COMSOL Multiphysics, and integrated into a system level code of the whole TRIEX-II circuit, developed using MATLAB/Simulink. The integration is carried out by implementing the COMSOL component into an S-function of MATLAB/Simulink, preserving the process flow diagram of the loop. In this way, it was possible to quantify the Q2 concentrations and the permeation fluxes, and to evaluate the theoretical extraction efficiency. The LiPb flow field inside the extractor was also derived. Finally, a comparison with the experimental results was performed. The results suggest that this tool could be adapted for analyses of complex systems, at a multiscale level, in view of design improvements and safety studies for the tritium cycle of ITER.}, language = {en}, - urldate = {2020-08-31}, - journal = {Journal of Nuclear Materials}, - author = {Sun, F. and Li, X. C. and Zhang, L. and Nakata, M. and Zhao, M. and Wada, T. and Yamazaki, S. and Koike, A. and Oya, Y.}, - month = aug, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Candido, Luigi and Cantore, Mattia and Galli, Edoardo and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, + month = jun, year = {2020}, - keywords = {Tungsten, Helium bubble, Diffusion barrier, Fusion, Hydrogen retention, Modeling and simulation, TDS}, - pages = {152227}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8AAFSH5I\\S0022311519315089.html:text/html}, + keywords = {WCLL, Multiscale, COMSOL, GLC, TRIEX-II, Tritium modelling}, + pages = {111585}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XIJF7PU5\\Candido et al. - 2020 - An integrated hydrogen isotopes transport model fo.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2X54R6B5\\S0920379620301332.html:text/html}, } -@article{yu_understanding_2020, - title = {Understanding hydrogen retention in damaged tungsten using experimentally-guided models of complex multispecies evolution}, - volume = {60}, - issn = {0029-5515, 1741-4326}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab9b3c}, - doi = {10.1088/1741-4326/ab9b3c}, +@article{charles_effect_2021, + title = {Effect of transient trapping on hydrogen transport near a blunting crack tip}, + issn = {0360-3199}, + url = {http://www.sciencedirect.com/science/article/pii/S036031992034787X}, + doi = {10.1016/j.ijhydene.2020.12.155}, + abstract = {The paper revisits the way transient trapping is introduced in the literature based on the Sofronis and McMeeking model (Sofronis and McMeeking, 1989) [1] of hydrogen transport. It is shown that the direct use of the improved formulation made by Krom et al. (1999) [2] for transient trapping may lead to non-physical results of hydrogen concentration in case of an insulated system. The use of McNabb and Foster trapping kinetic equation is more relevant, and its ability to model both trap creation and kinetic trapping is investigated on a Small Scale Yielding configuration for the sake of comparison with a reference case from the literature. A parametric study is conducted, exhibiting differences with literature, and emphasizes on the significant effect of trapping kinetics on the hydrogen distribution.}, language = {en}, - number = {9}, - urldate = {2020-08-07}, - journal = {Nuclear Fusion}, - author = {Yu, Qianran and Simmonds, Michael J. and Doerner, Russ. and Tynan, George R. and Yang, Li and Wirth, Brian D. and Marian, Jaime}, - month = sep, - year = {2020}, - pages = {096003}, - file = {Yu et al. - 2020 - Understanding hydrogen retention in damaged tungst.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HM8IA4X6\\Yu et al. - 2020 - Understanding hydrogen retention in damaged tungst.pdf:application/pdf}, + urldate = {2021-01-12}, + journal = {International Journal of Hydrogen Energy}, + author = {Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, + month = jan, + year = {2021}, + keywords = {Diffusion, Finite elements, Abaqus, Crack tip plasticity, Hydrogen trapping}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YR9K4J6Y\\S036031992034787X.html:text/html}, } -@article{entler_approximation_2018, - title = {Approximation of the economy of fusion energy}, - volume = {152}, - issn = {0360-5442}, - url = {http://www.sciencedirect.com/science/article/pii/S0360544218305395}, - doi = {10.1016/j.energy.2018.03.130}, - abstract = {Conceptual design activities of the first fusion power plants were launched in recent years with a view to putting them into operation by 2050. Nuclear fusion offers significant benefits in comparison with exploited energy sources, especially limitless fuel reserves, inherent nuclear safety, and negligible impact on the environment. The challenge is a high heat and neutron loading of the fusion reactors nuclear zone. The paper brings the ex-ante economic analysis of the fusion power plant model DEMO2 in terms of the cost of electricity. The model investment and operating costs are presented. The limit sales price of electricity was found using the net present value method. The levelized cost of electricity LCOE method with the inclusion of external costs is used for a comparison of selected power plant types based on the OECD statistical data and the EU ExternE project results. The comparison shows the levelized cost of electricity of fusion power plants competitive to the actual renewable resources. After internalisation of external costs, the fusion power plants should become even the second cheapest power source.}, +@article{ying_breeding_2018, + series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, + title = {Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation: {A} {MATLAB}/{Simulink}, {COMSOL} integrated dynamic tritium transport model for {HCCR} {TBS}}, + volume = {136}, + issn = {0920-3796}, + shorttitle = {Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618303879}, + doi = {10.1016/j.fusengdes.2018.04.093}, + abstract = {An integrated, multi-physics, dynamic predictive tool to quantify tritium retention, removal, and permeation for HCCR Test Blanket System (TBS) is presented in this paper. The tool expands from detailed COMSOL component models developed previously at UCLA, into an integrated, system-level blanket model using MATLAB/Simulink. It aims at achieving self-consistent predictions in particular concerning dynamic tritium concentration built-up in the He coolant. The integration is achieved by implementing COMSOL component models in the discrete section of Simulink S-Functions. The model replicates HCCR TBS process flow diagram and preserves main tritium flow characteristics for both helium cooling and tritium extraction systems. Current results demonstrate importance of detailed component models as well as dynamic simulation for improved accuracy on answers to questions related to safety/licensing and designs.}, language = {en}, - urldate = {2020-07-28}, - journal = {Energy}, - author = {Entler, Slavomir and Horacek, Jan and Dlouhy, Tomas and Dostal, Vaclav}, - month = jun, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Ying, Alice and Zhang, Hongjie and Merrill, Brad and Ahn, Mu-Young and Cho, Seungyon}, + month = nov, year = {2018}, - keywords = {Economy, External costs, Fusion energy, LCOE, NPV, Nuclear fusion}, - pages = {489--497}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MAJBXBC4\\Entler et al. - 2018 - Approximation of the economy of fusion energy.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ALF6VMWR\\S0360544218305395.html:text/html}, + keywords = {COMSOL, Simulink, Test blanket system, Tritium transport and permeation modeling}, + pages = {1153--1160}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\LWMJN9U5\\Ying et al. - 2018 - Breeding blanket system design implications on tri.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4TB27JJN\\S0920379618303879.html:text/html}, } -@article{gao_coupled_2018, - title = {A coupled rate theory-{Monte} {Carlo} model of helium bubble evolution in plasma-facing micro-engineered tungsten}, - volume = {509}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311518302095}, - doi = {10.1016/j.jnucmat.2018.04.051}, - abstract = {A multiscale model of helium bubble evolution in plasma-facing materials is developed. The model links different stages of helium bubble evolution: deposition, nucleation, growth, motion, and coalescence. Helium deposition is simulated with the SRIM Monte Carlo program to give spatial information on helium and displacement damage distributions near the surface. This deposition profile is then introduced into a space-dependent rate theory of bubble nucleation and growth to describe the early stages of the distribution and size of helium bubbles. The coarsening stage of bubble evolution as a result of whole bubble motion, interaction, and coalescence is modeled by a new Object Kinetic Monte Carlo (OKMC) model, for which initial conditions are taken from the mean-field rate theory calculations. The model is compared to experimental data on low-energy helium plasma interaction with micro-engineered tungsten (W), and on high-energy helium ion deposition in flat W samples. Novel features of the multiscale model include: (1) space-dependent rate theory; (2) OKMC model of bubble motion in stress and temperature fields; and (3) application of the model to micro-engineered materials, and comparison with experiments on the same time-scale. At low helium ion energy, it is found that the mechanism of trap mutation is essential in achieving good agreement with experimental measurements. On the other hand, good agreement with experiments at high incident ion energy and temperature showed the importance of bubble coalescence and coarsening as main mechanisms. The results of the model are compared with experiments on flat W surfaces irradiated at high ion energy (30 keV), and with micro-engineered W, where the surface is coated with high-density micro-pillars at low ion energy (around 100 eV). The predicted average bubble radius and density are in qualitative agreement with experimental results.}, +@article{pasler_development_2018, + title = {Development and verification of a component-level hydrogen transport model for a {DEMO}-like {HCPB} breeder unit with {OpenFOAM}}, + volume = {127}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618300103}, + doi = {10.1016/j.fusengdes.2018.01.008}, + abstract = {This work describes the development of a numerical model to simulate transient tritium transport on the breeder unit (BU) level for the EU helium cooled pebble bed (HCPB) concept for DEMO. The key output quantities of the model are the tritium concentration in the purge gas and in the coolant and the tritium inventory inside the BU structure. The model capabilities should cover normal operation as well as accident conditions. The Open Source Field Operation And Manipulation framework OpenFOAM serves as the basis for the model. Equations and boundary conditions required for hydrogen isotopes transport are implemented. Realistic properties data as diffusion constants and Sieverts constants are required, too. A key model issue is solid-fluid interface mass transfer. Two correlations that (1) approaches Sieverts equilibrium in the diffusion limit and (2) a rate dependent correlation that includes the diffusion limit for very high ad-/desorption rate constants are introduced. A two species interface mass transfer correlation based on the single species rate dependent correlation is developed, too. First verification calculations are compared to analytic solutions and TMAP calculations.}, language = {en}, - urldate = {2020-07-22}, - journal = {Journal of Nuclear Materials}, - author = {Gao, Edward and Ghoniem, Nasr M.}, - month = oct, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Pasler, Volker and Arbeiter, Frederik and Klein, Christine and Klimenko, Dmitry and Schlindwein, Georg and von der Weth, Axel}, + month = feb, year = {2018}, - pages = {577--590}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XP59YFBL\\Gao et Ghoniem - 2018 - A coupled rate theory-Monte Carlo model of helium .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HVGW2HM4\\S0022311518302095.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G4T5QSLT\\S0022311518302095.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WLD8DL4X\\Gao et Ghoniem - 2018 - A coupled rate theory-Monte Carlo model of helium .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PRDQJNAC\\S0022311518302095.html:text/html}, + keywords = {Tritium transport, HCPB, OpenFOAM, Safety}, + pages = {249--258}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\JNTLMS9Z\\Pasler et al. - 2018 - Development and verification of a component-level .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\V7V35MRT\\S0920379618300103.html:text/html}, } -@inproceedings{lassner_tungsten_1999, - title = {Tungsten: {Properties}, {Chemistry}, {Technology} of the {Element}, {Alloys}, and {Chemical} {Compounds}}, - shorttitle = {Tungsten}, - doi = {10.5860/choice.37-2788}, - abstract = {The Element Tungsten: Its Properties. Tungsten History: From Genesis to the 20th Century Products. Important Aspects of Tungsten Chemistry. Tungsten Compounds and Their Application. Industrial Production. Tungsten Alloys. Tungsten and Tungsten Alloy Products. Tungsten in Melting Metallurgy. Tungsten in Hard Metals. Tungsten in Catalysis. Tungsten Scrap Recycling. Ecology. Economy. Tungsten and Living Organisms. Index.}, - author = {Lassner, Erik and Schubert, Wolf-Dieter}, - year = {1999}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SKW8SIQS\\Lassner et Schubert - 1999 - Tungsten Properties, Chemistry, Technology of the.pdf:application/pdf}, +@article{zhang_integrated_2010, + series = {Proceedings of the {Ninth} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, + title = {Integrated simulation of tritium permeation in solid breeder blankets}, + volume = {85}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379610002309}, + doi = {10.1016/j.fusengdes.2010.05.018}, + abstract = {Numerical simulation of co-permeation of tritium and hydrogen from breeding zones to the coolant in the helium cooled pebble-bed blanket is performed in this paper. 3D multi-species convection–diffusion models integrated with thermal-fluid analysis in porous media are assessed and then used to estimate the associated tritium permeation for a solid breeder blanket module. Benchmark calculations give a reasonable agreement on the co-permeation rates with the experimental data. Simulation in a TBM unit show that purge gas flow can strongly affect tritium transport, increasing the purge flow velocity is an effective method to reduce tritium permeation to the coolant. In the case where hydrogen is added to the purge gas stream to promote tritium release, the co-permeation of H2, T2, and HT are taken into account in the permeation simulation, results show that permeation flux of T–T molecules is reduced due to the effect of co-permeation of hydrogen.}, + language = {en}, + number = {10}, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Zhang, Hongjie and Ying, Alice and Abdou, Mohamed A.}, + month = dec, + year = {2010}, + keywords = {Breeding blanket, 3D Model, Purge convection, Tritium permeation}, + pages = {1711--1715}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\P2BH9CFH\\Zhang et al. - 2010 - Integrated simulation of tritium permeation in sol.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\734QWLQ9\\S0920379610002309.html:text/html}, } -@techreport{dolan_assessment_1994, - title = {Assessment of database for interaction of tritium with {ITER} plasma facing materials}, - url = {http://www.osti.gov/servlets/purl/10191406-mAzpKL/webviewable/}, +@article{nicholas_re-examining_2021, + title = {Re-examining the role of nuclear fusion in a renewables-based energy mix}, + volume = {149}, + issn = {0301-4215}, + url = {http://www.sciencedirect.com/science/article/pii/S0301421520307540}, + doi = {10.1016/j.enpol.2020.112043}, + abstract = {Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineering and materials science will still impose significant constraints on the characteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the significant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fusion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation.}, language = {en}, - number = {EGG-FSP--11348, 10191406}, - urldate = {2019-11-22}, - author = {Dolan, T.J. and Anderl, R.A.}, - month = sep, - year = {1994}, - doi = {10.2172/10191406}, - pages = {EGG--FSP--11348, 10191406}, - file = {Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A4ED7EDZ\\Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:application/pdf;Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QEFG3RDK\\Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9SKIYWB3\\webviewable.html:text/html}, + urldate = {2021-01-06}, + journal = {Energy Policy}, + author = {Nicholas, T. E. G. and Davis, T. P. and Federici, F. and Leland, J. and Patel, B. S. and Vincent, C. and Ward, S. H.}, + month = feb, + year = {2021}, + keywords = {Fusion, Decarbonisation, EROI, Firm resources, Load-following, Nuclear, Perceptions, Waste}, + pages = {112043}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\JMMM75FH\\Nicholas et al. - 2021 - Re-examining the role of nuclear fusion in a renew.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\M4HEEKWE\\S0301421520307540.html:text/html}, } -@article{temmerman_influence_2018, - title = {The influence of plasma-surface interaction on the performance of tungsten at the {ITER} divertor vertical targets}, - volume = {60}, - issn = {0741-3335}, - url = {https://doi.org/10.1088%2F1361-6587%2Faaaf62}, - doi = {10.1088/1361-6587/aaaf62}, - abstract = {The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed to high fluxes of low-energy particles (e.g. H, D, T, He, Ne and/or N). Combined with long-pulse operations, this implies fluences well in excess of the highest values reached in today’s tokamak experiments. Shaping of the individual monoblock top surface and tilting of the vertical targets for leading-edge protection lead to an increased surface heat flux, and thus increased surface temperature and a reduced margin to remain below the temperature at which recrystallization and grain growth begin. Significant morphology changes are known to occur on W after exposure to high fluences of low-energy particles, be it H or He. An analysis of the formation conditions of these morphology changes is made in relation to the conditions expected at the vertical targets during different phases of operations. It is concluded that both H and He-related effects can occur in ITER. In particular, the case of He-induced nanostructure (also known as ‘fuzz’) is reviewed. Fuzz formation appears possible over a limited region of the outer vertical target, the inner target being generally a net Be deposition area. A simple analysis of the fuzz growth rate including the effect of edge-localized modes (ELMs) and the reduced thermal conductivity of fuzz shows that the fuzz thickness is likely to be limited by the occurrence of annealing during ELM-induced thermal excursions. Not only the morphology, but the material mechanical and thermal properties can be modified by plasma exposure. A review of the existing literature is made, but the existing data are insufficient to conclude quantitatively on the importance and extent of these effects for ITER. As a consequence of the high surface temperatures in ITER, W recrystallization is an important effect to consider, since it leads to a decrease in material strength. An approach is proposed here to develop an operational budget for the W material, i.e. the time the divertor material can be operated at a given temperature before a significant fraction of the material is recrystallized. In general, while it is clear that significant surface damage can occur during ITER operations, the tolerable level of damage in terms of plasma operations currently remains unknown.}, - language = {en}, - number = {4}, - urldate = {2020-06-03}, - journal = {Plasma Physics and Controlled Fusion}, - author = {Temmerman, G. De and Hirai, T. and Pitts, R. A.}, - month = mar, - year = {2018}, - note = {Publisher: IOP Publishing}, - pages = {044018}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L9V2JQ2K\\Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf;IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6ZPP7I4S\\Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf;De Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MTX484WV\\De Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf}, +@misc{noauthor_breeding_nodate, + title = {Breeding {Blankets} - an overview {\textbar} {ScienceDirect} {Topics}}, + url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/topics/engineering/breeding-blankets}, + urldate = {2020-12-14}, + file = {Breeding Blankets - an overview | ScienceDirect Topics:D\:\\Logiciels\\data_zotero\\storage\\IIENABQN\\breeding-blankets.html:text/html}, } -@article{bonny_binding_2014, - title = {On the binding of nanometric hydrogen–helium clusters in tungsten}, - volume = {26}, - issn = {0953-8984}, - url = {https://doi.org/10.1088%2F0953-8984%2F26%2F48%2F485001}, - doi = {10.1088/0953-8984/26/48/485001}, - abstract = {In this work we developed an embedded atom method potential for large scale atomistic simulations in the ternary tungsten–hydrogen–helium (W–H–He) system, focusing on applications in the fusion research domain. Following available ab initio data, the potential reproduces key interactions between H, He and point defects in W and utilizes the most recent potential for matrix W. The potential is applied to assess the thermal stability of various H–He complexes of sizes too large for ab initio techniques. The results show that the dissociation of H–He clusters stabilized by vacancies will occur primarily by emission of hydrogen atoms and then by break-up of V–He complexes, indicating that H–He interaction does influence the release of hydrogen.}, +@article{rubel_fusion_2019, + title = {Fusion {Neutrons}: {Tritium} {Breeding} and {Impact} on {Wall} {Materials} and {Components} of {Diagnostic} {Systems}}, + volume = {38}, + issn = {1572-9591}, + shorttitle = {Fusion {Neutrons}}, + url = {https://doi.org/10.1007/s10894-018-0182-1}, + doi = {10.1007/s10894-018-0182-1}, + abstract = {A concise overview is given on the impact of fusion neutrons on various classes of materials applied in reactor technology: plasma-facing, structural and functional tested for tritium production and for diagnostic systems. Tritium breeding in the reactor blanket, fuel cycle and separation of hydrogen isotopes are described together with issues related to primary (tritium) and induced radioactivity. Neutron-induced damage and degradation of material properties are addressed. Material testing under neutron fluxes and safety issues associated with handling components in the radioactive environment are described. A comprehensive list of references to monographs and research papers is included to help navigation in literature.}, language = {en}, - number = {48}, - urldate = {2020-07-21}, - journal = {Journal of Physics: Condensed Matter}, - author = {Bonny, G. and Grigorev, P. and Terentyev, D.}, - month = oct, - year = {2014}, - note = {Publisher: IOP Publishing}, - pages = {485001}, - file = {Bonny et al. - 2014 - On the binding of nanometric hydrogen–helium clust.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z5E54IB2\\Bonny et al. - 2014 - On the binding of nanometric hydrogen–helium clust.pdf:application/pdf}, + number = {3}, + urldate = {2020-12-14}, + journal = {Journal of Fusion Energy}, + author = {Rubel, Marek}, + month = aug, + year = {2019}, + pages = {315--329}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HDW2QJ4C\\Rubel - 2019 - Fusion Neutrons Tritium Breeding and Impact on Wa.pdf:application/pdf}, } -@article{wang_morphologies_2017, - title = {Morphologies of tungsten nanotendrils grown under helium exposure}, - volume = {7}, - copyright = {2017 The Author(s)}, - issn = {2045-2322}, - url = {https://www.nature.com/articles/srep42315}, - doi = {10.1038/srep42315}, - abstract = {Nanotendril “fuzz” will grow under He bombardment under tokamak-relevant conditions on tungsten plasma-facing materials in a magnetic fusion energy device. We have grown tungsten nanotendrils at low (50 eV) and high (12 keV) He bombardment energy, in the range 900–1000 °C, and characterized them using electron microscopy. Low energy tendrils are finer ({\textasciitilde}22 nm diameter) than high-energy tendrils ({\textasciitilde}176 nm diameter), and low-energy tendrils have a smoother surface than high-energy tendrils. Cavities were omnipresent and typically {\textasciitilde}5–10 nm in size. Oxygen was present at tendril surfaces, but tendrils were all BCC tungsten metal. Electron diffraction measured tendril growth axes and grain boundary angle/axis pairs; no preferential growth axes or angle/axis pairs were observed, and low-energy fuzz grain boundaries tended to be high angle; high energy tendril grain boundaries were not observed. We speculate that the strong tendency to high-angle grain boundaries in the low-energy tendrils implies that as the tendrils twist or bend, strain must accumulate until nucleation of a grain boundary is favorable compared to further lattice rotation. The high-energy tendrils consisted of very large ({\textgreater}100 nm) grains compared to the tendril size, so the nature of the high energy irradiation must enable faster growth with less lattice rotation.}, +@article{federici_overview_2019, + title = {An overview of the {EU} breeding blanket design strategy as an integral part of the {DEMO} design effort}, + volume = {141}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379619301590}, + doi = {10.1016/j.fusengdes.2019.01.141}, + abstract = {This paper provides an overview of the newly revised design and development strategy for the DEMO breeding blanket in Europe. This has been defined to take into account the input from the DEMO pre-conceptual design activities, the findings and recommendations of a thorough technical and programmatic assessment of the breeding blanket and the EU ITER Test Blanket Module (TBM) programs, conducted in 2017 by an independent expert panel. This work has led to the identification of (i) the most mature and technically sound breeding blanket concepts to be used as “driver” and “advanced” breeding blankets in DEMO, the latter to be installed and tested in a limited number of properly designed segments, potentially being more attractive for future fusion power plants; (ii) the remaining technical gaps and R\&D priorities. A number of urgent steps that are required to better align and strengthen the EU TBM and DEMO Breeding Blanket Program as a whole and to aim at an efficient implementation of the work are described in this paper. These include a proposal to change the EU TBM options to be tested in ITER in order to obtain important and useful information from the two current breeders (solid and liquid) and coolants (helium and water) considered for DEMO.}, language = {en}, - number = {1}, - urldate = {2020-06-29}, - journal = {Scientific Reports}, - author = {Wang, Kun and Doerner, R. P. and Baldwin, M. J. and Meyer, F. W. and Bannister, M. E. and Darbal, Amith and Stroud, Robert and Parish, Chad M.}, - month = feb, - year = {2017}, - note = {Number: 1 -Publisher: Nature Publishing Group}, - pages = {42315}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D9DPCDAF\\srep42315.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\T57DCU6G\\Wang et al. - 2017 - Morphologies of tungsten nanotendrils grown under .pdf:application/pdf}, + urldate = {2020-12-14}, + journal = {Fusion Engineering and Design}, + author = {Federici, G. and Boccaccini, L. and Cismondi, F. and Gasparotto, M. and Poitevin, Y. and Ricapito, I.}, + month = apr, + year = {2019}, + keywords = {DEMO, Tritium, Breeding blanket, Design integration, Power plant}, + pages = {30--42}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\RZNLSBXH\\Federici et al. - 2019 - An overview of the EU breeding blanket design stra.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\38H82YQF\\S0920379619301590.html:text/html}, } -@article{hammond_theoretical_2020, - title = {Theoretical {Model} of {Helium} {Bubble} {Growth} and {Density} in {Plasma}-{Facing} {Metals}}, - volume = {10}, - copyright = {2020 The Author(s)}, - issn = {2045-2322}, - url = {https://www.nature.com/articles/s41598-020-58581-8}, - doi = {10.1038/s41598-020-58581-8}, - abstract = {We present a theoretically-motivated model of helium bubble density as a function of volume for high-pressure helium bubbles in plasma-facing tungsten. The model is a good match to the empirical correlation we published previously [Hammond et al., Acta Mater. 144, 561–578 (2018)] for small bubbles, but the current model uses no adjustable parameters. The model is likely applicable to significantly larger bubbles than the ones examined here, and its assumptions can be extended trivially to other metals and gases. We expect the model to be broadly applicable and useful in coarse-grained models of gas transport in metals.}, +@article{aubert_design_2020, + title = {Design and preliminary analyses of the new {Water} {Cooled} {Lithium} {Lead} {TBM} for {ITER}}, + volume = {160}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620304695}, + doi = {10.1016/j.fusengdes.2020.111921}, + abstract = {In the European strategy, DEMO is the intermediate step between ITER and a commercial fusion power plant. In this framework, one of the goal of DEMO is to be a Breeding Blanket test facility. The Breeding Blanket, which is not present in ITER, is one of the key components for the future deployment of nuclear fusion electricity as it accomplishes the functions of tritium breeding and nuclear to thermal power conversion. Due to time constraints lead by the construction schedule of DEMO, a new strategy to consider in DEMO a “driver” Breeding Blanket that needs limited technological extrapolation has been chosen, while “advanced” Breeding Blanket concepts will be tested in the next phases. In this context, ITER will allow to test technologies to provide relevant contributions in terms of Return of eXperience to the DEMO “driver” Breeding Blanket project by the mean of Test Blanket Modules (TBM) to be installed in different ITER Vacuum Vessel Ports. Among the possible “driver” Breeding Blanket, the Water Cooled Lithium Lead (WCLL) concept comes out. In this framework, a realignment of the DEMO Breeding Blanket and TBM programs has started in 2017, leading to a new TBM development relevant of the DEMO WCLL BB. The WCLL TBM is therefore an essential component in ITER that will provide crucial information for the development of the DEMO “driver” blanket. This paper aims at presenting the development process and design status of WCLL TBM. After recalling the main features of the WCLL TBM, conceptual design analyses are presented and discussed.}, language = {en}, - number = {1}, - urldate = {2020-06-29}, - journal = {Scientific Reports}, - author = {Hammond, Karl D. and Maroudas, Dimitrios and Wirth, Brian D.}, - month = feb, + urldate = {2020-12-14}, + journal = {Fusion Engineering and Design}, + author = {Aubert, J. and Aiello, G. and Alonso, D. and Batal, T. and Boullon, R. and Burles, S. and Cantone, B. and Cismondi, F. and Del Nevo, A. and Maqueda, L. and Morin, A. and Rodríguez, E. and Rueda, F. and Soldaini, M. and Vallory, J.}, + month = nov, year = {2020}, - note = {Number: 1 -Publisher: Nature Publishing Group}, - pages = {2192}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QHFTARND\\s41598-020-58581-8.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YJ88ABJP\\Hammond et al. - 2020 - Theoretical Model of Helium Bubble Growth and Dens.pdf:application/pdf}, + keywords = {ITER, WCLL, Breeding Blanket, TBM}, + pages = {111921}, + file = {Aubert et al. - 2020 - Design and preliminary analyses of the new Water C.pdf:D\:\\Logiciels\\data_zotero\\storage\\4IR47KT8\\Aubert et al. - 2020 - Design and preliminary analyses of the new Water C.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ACGSCMZQ\\S0920379620304695.html:text/html}, } -@article{ogorodnikova_deuterium_2011, - title = {Deuterium retention in tungsten exposed to low-energy pure and helium-seeded deuterium plasmas}, - volume = {109}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.3505754}, - doi = {10.1063/1.3505754}, - number = {1}, - urldate = {2020-06-24}, - journal = {Journal of Applied Physics}, - author = {Ogorodnikova, O. V. and Schwarz-Selinger, T. and Sugiyama, K. and Alimov, V. Kh.}, - month = jan, - year = {2011}, - note = {Publisher: American Institute of Physics}, - pages = {013309}, - file = {Ogorodnikova et al. - 2011 - Deuterium retention in tungsten exposed to low-ene.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XGV2R2KV\\Ogorodnikova et al. - 2011 - Deuterium retention in tungsten exposed to low-ene.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KEYPVZ2A\\1.html:text/html}, +@article{aubert_status_2018, + series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, + title = {Status of the {EU} {DEMO} {HCLL} breeding blanket design development}, + volume = {136}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S092037961830423X}, + doi = {10.1016/j.fusengdes.2018.04.133}, + abstract = {In the framework of the European “HORIZON 2020” innovation and research programme, the EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO). One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. CEA-Saclay, with the support of Wigner-RCP and Centrum výzkumu Řež, is in charge of the development of one of the four BB concepts investigated in Europe for DEMO: the Helium Cooled Lithium Lead (HCLL) BB. The rationales of the HCLL are the use of Eurofer as structural material, eutectic liquid lithium-lead (PbLi) as tritium breeder and neutron multiplier, and helium gas as coolant. This paper shows the basic description of the DEMO HCLL BB concept and its design evolution during the past years, from a design based on the ITER Test Blanket Module (TBM) concept to a more advanced design called “Advanced-Plus” concept. This new HCLL BB concept that has been designed in order to improve Tritium Breeding Ratio (TBR) and shielding performances is presented. This new reference HCLL BB design has been analyzed and show very promising nuclear performances. Nevertheless, the “Optimized Conservative” concept, based on ITER TBM, is still considered as a robust back-up solution since structural improvements are still necessary on the “Advanced-Plus” concept. Moreover, a new Back Supporting Structure (BSS) is presented in this paper, designed to support the BB modules, with the aim to reduce pressure drops and thermal stresses.}, + language = {en}, + urldate = {2020-12-14}, + journal = {Fusion Engineering and Design}, + author = {Aubert, Julien and Aiello, Giacomo and Arena, Pietro and Barrett, Tom and Boccaccini, Lorenzo Virgilio and Bongiovì, Gaetano and Boullon, Rémi and Cismondi, Fabio and Critescu, Ion and Domalapally, Phani Kumar and Forest, Laurent and Jaboulay, Jean-Charles and Kiss, Béla and Morin, Alexandre and Peyraud, Justine and Porempovics, Gabor and Utili, Marco and Vála, Ladislav}, + month = nov, + year = {2018}, + keywords = {DEMO, Breeding Blanket, HCLL}, + pages = {1428--1432}, + file = {Aubert et al. - 2018 - Status of the EU DEMO HCLL breeding blanket design.pdf:D\:\\Logiciels\\data_zotero\\storage\\F48N9ABH\\Aubert et al. - 2018 - Status of the EU DEMO HCLL breeding blanket design.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MYBZFDWH\\S092037961830423X.html:text/html}, } -@article{sun_synergistic_2020, - title = {Synergistic effects of high energy helium irradiation and damage introduction at high temperature on hydrogen isotope retention in plasma facing materials}, - volume = {533}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311519313017}, - doi = {10.1016/j.jnucmat.2020.152122}, - abstract = {In this study, energetic helium (He) ion irradiation was performed to obtain bulk He distribution in tungsten (W) materials, concurrent with damage introduction at high temperature. Then, deuterium (D) implantation and thermal desorption spectrometry were performed to evaluate D retention. At the same time, the surface tritium (T) concentration and depth distribution were evaluated by imaging plate (IP) and β-ray induced X-ray spectroscopy (BIXS) measurements after mixed D-T gas exposure. Numerical simulations were applied to evaluate changes in binding energies, diffusion depths, and trapping sites under different irradiation conditions. The results showed that weak trapping sites with higher concentration, such as vacancies, were produced during only energetic He+ irradiation events, leading to enhancement of D retention. Fe3+-He+ simultaneous irradiation promoted the formation of HexVy complexes, which reduced the concentration of vacancy trapping sites and changed the stress field around defects, leading to the suppression of D trapping behavior. From the reduced effects of D retention caused by HexVy complexes at higher temperatures, the results suggested that defect recovery was the dominant mechanism. With increasing damage level at higher temperatures, more weak trapping sites, such as dislocations and vacancies sites, were produced, leading to a more dominant influence on D retention than HexVy complex effects. It was also found that HexVy complexes prevented D diffusion to the bulk and that simulation results showed that the damage level had little impact on D diffusion depth.}, - language = {en}, - urldate = {2020-06-24}, - journal = {Journal of Nuclear Materials}, - author = {Sun, F. and Nakata, M. and Lee, S. E. and Zhao, M. and Wada, T. and Yamazaki, S. and Koike, A. and Kondo, S. and Hinoki, T. and Hara, M. and Oya, Y.}, - month = may, +@article{boullon_development_2020, + title = {Development of a {WCLL} {DEMO} {First} {Wall} design module in the {SYCOMORE} system code interfaced with the neutronic one}, + volume = {153}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620300624}, + doi = {10.1016/j.fusengdes.2020.111514}, + abstract = {The pre-conceptual design of the DEMOnstration reactors has already started and several tokamak configurations have to be tested to find the best design by exploring different design parameters. Fast simulations involving the different components behavior must be performed. Within the European framework, SYCOMORE (SYstem COde for MOdelling tokamak REactor) is developed by CEA for this purpose. The Breeding Blanket (BB) facing the plasma is a key component in DEMO ensuring tritium self-sufficiency, shielding against neutrons and heat extraction for electricity production. Several BB concepts are being studied, among which the Water Cooled Lithium Lead (WCLL) one. SYCOMORE includes several specific modules in Python linked together, one of which has been developed to define a suitable design of the WCLL Breeding Blanket and is presented in this paper. The method to define automatically the WCLL First Wall (FW) design using analytical design formulae starting from thermo-hydraulic and thermo-mechanical considerations as well as design criteria coming from Codes \& Standards (C\&S) is presented. Furthermore WCLL FW design obtained with SYCOMORE is compared to Finite Elements (FE) analyses of the DEMO WCLL BB. Finally, a coupling between thermo-mechanics and neutronics is implemented, several iterations are necessary to obtain a converged design. Neutronic block evaluates the radial build, the BB tritium production, and the nuclear heating in the FW and the Breeding Zone (used by thermo-mechanical block). Thermo-mechanical module gives the design data (FW thickness, compositions, etc.) to the neutronic block.}, + language = {en}, + urldate = {2020-12-14}, + journal = {Fusion Engineering and Design}, + author = {Boullon, Rémi and Aubert, Julien and Jaboulay, Jean-Charles and Aiello, Giacomo}, + month = apr, year = {2020}, - keywords = {Helium, Tungsten, Simulation, Hydrogen isotope, Fusion, Irradiation damages, TDS}, - pages = {152122}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H4BAXPEY\\Sun et al. - 2020 - Synergistic effects of high energy helium irradiat.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3PHR77IB\\S0022311519313017.html:text/html}, + keywords = {DEMO, WCLL, Breeding blanket, SYCOMORE, System code}, + pages = {111514}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\9W4U2CZL\\Boullon et al. - 2020 - Development of a WCLL DEMO First Wall design modul.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4T29JJMD\\S0920379620300624.html:text/html}, } -@article{pitts_physics_2019, - title = {Physics basis for the first {ITER} tungsten divertor}, - volume = {20}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179119300237}, - doi = {10.1016/j.nme.2019.100696}, - abstract = {On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ∼50\% higher than the previously accepted value of ∼10 MW m−2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events.}, - language = {en}, - urldate = {2020-06-24}, - journal = {Nuclear Materials and Energy}, - author = {Pitts, R. A. and Bonnin, X. and Escourbiac, F. and Frerichs, H. and Gunn, J. P. and Hirai, T. and Kukushkin, A. S. and Kaveeva, E. and Miller, M. A. and Moulton, D. and Rozhansky, V. and Senichenkov, I. and Sytova, E. and Schmitz, O. and Stangeby, P. C. and De Temmerman, G. and Veselova, I. and Wiesen, S.}, - month = aug, - year = {2019}, - keywords = {Tungsten, Divertor, Heat fluxes, ITER, SOLPS}, - pages = {100696}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\C5UCVAZA\\Pitts et al. - 2019 - Physics basis for the first ITER tungsten divertor.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9BNNLRW3\\S2352179119300237.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FCM9SWUK\\Pitts et al. - 2019 - Physics basis for the first ITER tungsten divertor.pdf:application/pdf}, +@article{bergstrom_molecular_2017, + title = {A {Molecular} {Dynamics} {Study} of {Subsurface} {Hydrogen}-{Helium} {Bubbles} in {Tungsten}}, + volume = {71}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST16-121}, + doi = {10.13182/FST16-121}, + abstract = {Fusion reactor materials experience high ion fluxes and operating temperatures, which will ultimately produce subsurface helium and hydrogen bubbles in the tungsten divertor that can cause surface degradation and impact core plasma performance. Molecular dynamics simulations have been used to evaluate the behavior of hydrogen and helium near a 2-nm bubble or void below a tungsten surface as a function of surface orientation, temperature, gas atom concentration, initial hydrogen distribution, and depth below the surface. A clear tendency for hydrogen to segregate to the bubble-matrix interface is observed in these simulations, regardless of the initial spatial distribution of the hydrogen or simulation parameters. This segregation is due in part to a local minimum in the hydrogen energy at the periphery of the bubble. Further work is required to fully characterize the mechanism of this behavior and to assess the quantities of hydrogen in the bubble and at the bubble periphery.}, + number = {1}, + urldate = {2019-10-07}, + journal = {Fusion Science and Technology}, + author = {Bergstrom, Z. J. and Cusentino, M. A. and Wirth, B. D.}, + month = jan, + year = {2017}, + keywords = {helium bubbles, hydrogen retention, Molecular Dynamics, Plasma-surface interactions}, + pages = {122--135}, + annote = {Energie de liaison entre 1.5 et 2.5 eV}, + file = {Bergstrom et al. - 2017 - A Molecular Dynamics Study of Subsurface Hydrogen-.pdf:D\:\\Logiciels\\data_zotero\\storage\\ARFFB7TA\\Bergstrom et al. - 2017 - A Molecular Dynamics Study of Subsurface Hydrogen-.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\X64CDL52\\FST16-121.html:text/html}, } -@article{alimov_depth_2005, - series = {{PSI}-16}, - title = {Depth distribution of deuterium in single- and polycrystalline tungsten up to depths of several micrometers}, - volume = {337-339}, +@article{causey_hydrogen_2002, + title = {Hydrogen isotope retention and recycling in fusion reactor plasma-facing components}, + volume = {300}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311504007986}, - doi = {10.1016/j.jnucmat.2004.10.082}, - abstract = {Depth profiles of deuterium trapped in W single crystals and polycrystalline W irradiated with 200eV D ions at 300–323K have been measured up to a depth of 7μm using the D(3He,p)4He nuclear reaction in a resonance-like technique. The proton yield as a function of incident 3He energy was measured and the D depth profile was obtained by deconvolution of the measured proton yields using the program simnra. The depth at which deuterium is retained can be tentatively divided into three zones: (i) the near-surface layer (up to a depth of ∼0.2μm), (ii) the sub-surface layer (from ∼0.5 to ∼2μm), and (iii) the bulk ({\textgreater}5μm). Low-energy D ion irradiation modifies the W structure to depths of up to about 5μm, both for W single crystals and polycrystalline W. Up to this depth trapping sites are created at a fluence of 5×1022/m2 for the retention of deuterium at about 0.1at.\%.}, - language = {en}, - urldate = {2020-06-23}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311501007322}, + doi = {10.1016/S0022-3115(01)00732-2}, + abstract = {The proper design of a fusion reactor is not possible unless there is an understanding of the hydrogen isotope retention and recycling for the plasma-facing components. From the tritium inventory point of view, it is absolutely necessary to understand the short-term and long-term hydrogen isotopes retention characteristics of the individual materials used for the first wall and divertor. From the plasma density and fueling point of view, it is necessary to understand the recycling characteristics of these materials. This report is an overview of the available data on hydrogen isotope retention and recycling for beryllium, tungsten, carbon, and selected liquid metals. For each material discussed, recommendations are made as to the most appropriate values to use for parameters such as diffusivity, solubility, recombination rate coefficient, and trapping.}, + number = {2}, + urldate = {2019-10-07}, journal = {Journal of Nuclear Materials}, - author = {Alimov, V. Kh. and Roth, J. and Mayer, M.}, - month = mar, - year = {2005}, - keywords = {Tungsten, Deuterium inventory}, - pages = {619--623}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PZGXP4ID\\Alimov et al. - 2005 - Depth distribution of deuterium in single- and pol.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IGVE89AQ\\S0022311504007986.html:text/html}, + author = {Causey, Rion A}, + month = feb, + year = {2002}, + keywords = {Experiment}, + pages = {91--117}, + file = {Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:D\:\\Logiciels\\data_zotero\\storage\\BVB4EWBA\\Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Y4ZM8B4Y\\Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\8KN2HJM4\\S0022311501007322.html:text/html}, } -@article{li_review_2020, - title = {A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten}, - issn = {2661-8036}, - url = {https://doi.org/10.1007/s42864-020-00042-w}, - doi = {10.1007/s42864-020-00042-w}, - abstract = {The change in surface damage/microstructures and its effects on the hydrogen (H) isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten (W)-based plasma-facing materials (PFMs) in fusion such as surface erosion, H/He retention and tritium (T) inventory. Complex surface damage/microstructures are introduced in W by high-temperature plasma irradiation and new material design, typically including pre-damage and multi-ion co-deposition induced structures, solute elements and related composites, native defects like dislocations and interfaces, and nanostructures. Systematic experimental and theoretical researches were performed on H isotope/He retention in complex W-based materials in the past decades. In this review, we aim to provide an overview of typical surface damage/microstructures and their effects on H/He retention in W, both in the experiment and multiscale modeling. The distribution/state, dynamics evolution, and interaction with defects/microstructures of H/He are generally summarized at different scales. Finally, the current difficulties, challenges and future directions are also discussed about H/He retention in complex W-based PFMs.}, +@article{liu_examination_2016, + title = {An examination on the direct concentration approach to simulating moisture diffusion in a multi-material system}, + volume = {60}, + issn = {0026-2714}, + url = {http://www.sciencedirect.com/science/article/pii/S0026271416300476}, + doi = {10.1016/j.microrel.2016.03.012}, + abstract = {In 2009, Xie et al. proposed a diffusion simulation method called direct concentration approach (DCA), which aimed at solving moisture diffusion problems in electronic packages under a transient temperature environment such as reflow process (“Direct Concentration Approach of Moisture Diffusion and Whole Field Vapor Pressure Modeling for Reflow Process: Part I — Theory and Numerical Implementation,” ASME J. Electron. Packag., 131, p. 031,010). However, our study shows that although the DCA may give reasonably accurate concentration results under several circumstances, its relative error in concentration result can be as high as 10\% in one of our test cases. More importantly, the DCA generally leads to the discontinuity of diffusion flux at the bi-material interface, which means that the result may violate the law of mass conservation. A theoretical derivation based on a one-dimensional (1-D) diffusion case is presented to demonstrate the flaw of the DCA using the finite element formulation.}, language = {en}, - urldate = {2020-06-23}, - journal = {Tungsten}, - author = {Li, Yong-Gang and Zheng, Qi-Rong and Wei, Liu-Ming and Zhang, Chuan-Guo and Zeng, Zhi}, - month = jun, - year = {2020}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9WNJDIMF\\Li et al. - 2020 - A review of surface damagemicrostructures and the.pdf:application/pdf}, + urldate = {2020-05-28}, + journal = {Microelectronics Reliability}, + author = {Liu, Dapeng and Wang, Jing and Liu, Ruiyang and Park, S. B.}, + month = may, + year = {2016}, + keywords = {Moisture diffusion model, Packaging reliability, Simulation}, + pages = {109--115}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\CGHT7FPM\\Liu et al. - 2016 - An examination on the direct concentration approac.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VYFE8HYM\\S0026271416300476.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SZJ5KX7R\\S0026271416300476.html:text/html}, } -@article{buzi_deuterium_2019, - title = {Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys}, - volume = {21}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179119300584}, - doi = {10.1016/j.nme.2019.100713}, - abstract = {Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.}, +@article{marchi_permeability_2007, + title = {Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures}, + volume = {32}, + issn = {0360-3199}, + url = {http://www.sciencedirect.com/science/article/pii/S0360319906001753}, + doi = {10.1016/j.ijhydene.2006.05.008}, + abstract = {In this report, we provide a framework for describing the permeability, solubility and diffusivity of hydrogen and its isotopes in austenitic stainless steels at temperatures and high gas pressures of engineering interest for hydrogen storage and distribution infrastructure. We demonstrate the importance of using the real gas behavior for modeling permeation and dissolution of hydrogen under these conditions. A simple one-parameter equation of state (the Abel–Noble equation of state) is shown to capture the real gas behavior of hydrogen and its isotopes for pressures less than 200MPa and temperatures between 223 and 423K. We use the literature on hydrogen transport in austenitic stainless steels to provide general guidance on and clarification of test procedures, and to provide recommendations for appropriate permeability, diffusivity and solubility relationships for austenitic stainless steels. Hydrogen precharging and concentration measurements for a variety of austenitic stainless steels are described and used to generate more accurate solubility and diffusivity relationships.}, language = {en}, - urldate = {2020-06-23}, - journal = {Nuclear Materials and Energy}, - author = {Buzi, L. and Yeh, M. and Yeh, Y-W. and Donaldson, O. K. and Patino, M. I. and Trelewicz, J. R. and Yao, N. and Doerner, R. and Koel, B. E.}, - month = dec, - year = {2019}, - keywords = {Helium, Tungsten, Deuterium, Plasma-facing materials}, - pages = {100713}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IFFWVYM6\\Buzi et al. - 2019 - Deuterium and helium ion irradiation of nanograine.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W9ISQLI3\\S2352179119300584.html:text/html}, + number = {1}, + urldate = {2020-09-21}, + journal = {International Journal of Hydrogen Energy}, + author = {Marchi, C. San and Somerday, B. P. and Robinson, S. L.}, + month = jan, + year = {2007}, + keywords = {Solubility, Diffusivity, High-pressure hydrogen gas, Hydrogen isotopes, Permeability}, + pages = {100--116}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\UHUN39Y2\\Marchi et al. - 2007 - Permeability, solubility and diffusivity of hydrog.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZV87U7TW\\S0360319906001753.html:text/html}, } -@article{dwivedi_hydrogen_2018, - title = {Hydrogen embrittlement in different materials: {A} review}, - volume = {43}, - issn = {0360-3199}, - shorttitle = {Hydrogen embrittlement in different materials}, - url = {http://www.sciencedirect.com/science/article/pii/S0360319918331306}, - doi = {10.1016/j.ijhydene.2018.09.201}, - abstract = {Hydrogen embrittlement (HE) is a widely known phenomenon in high strength materials. HE is responsible for subcritical crack growth in material, fracture initiation and catastrophic failure with subsequent loss in mechanical properties such as ductility, toughness and strength. This hydrogen is induced in the material during electrochemical reaction and high-pressure gaseous hydrogen environment. LIST, SSRT and TDS techniques are performed to know the effect in mechanical properties and amount of hydrogen available in the material. For microstructure examination SEM, FESEM and TEM are performed to know the effect of hydrogen in the internal crystal structure. Also, various mechanisms which are responsible for crack growth and final fracture are discussed. This paper deals with HE definition, mechanisms which causes HE, subcritical crack growth, the concentration of hydrogen measurement and prevention activities are discussed which act as a barrier for hydrogen diffusion.}, +@article{shimada_tritium_2017, + series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, + title = {Tritium decay helium-3 effects in tungsten}, + volume = {12}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179116302095}, + doi = {10.1016/j.nme.2016.11.006}, + abstract = {Tritium (T) implanted by plasmas diffuses into bulk material, especially rapidly at elevated temperatures, and becomes trapped in neutron radiation-induced defects in materials that act as trapping sites for the tritium. The trapped tritium atoms will decay to produce helium-3 (3He) atoms at a half-life of 12.3 years. 3He has a large cross section for absorbing thermal neutrons, which after absorbing a neutron produces hydrogen (H) and tritium ions with a combined kinetic energy of 0.76 MeV through the 3He(n,H)T nuclear reaction. The purpose of this paper is to quantify the 3He produced in tungsten by tritium decay compared to the neutron-induced helium-4 (4He) produced in tungsten. This is important given the fact that helium in materials not only creates microstructural damage in the bulk of the material but alters surface morphology of the material effecting plasma-surface interaction process (e.g. material evolution, erosion and tritium behavior) of plasma-facing component materials. Effects of tritium decay 3He in tungsten are investigated here with a simple model that predicts quantity of 3He produced in a fusion DEMO FW based on a neutron energy spectrum found in literature. This study reveals that: (1) helium-3 concentration was equilibrated to ∼6\% of initial/trapped tritium concentration, (2) tritium concentration remained approximately constant (94\% of initial tritium concentration), and (3) displacement damage from 3He(n,H)T nuclear reaction became {\textgreater}1 dpa/year in DEMO FW.}, language = {en}, - number = {46}, - urldate = {2020-06-19}, - journal = {International Journal of Hydrogen Energy}, - author = {Dwivedi, Sandeep Kumar and Vishwakarma, Manish}, - month = nov, - year = {2018}, - keywords = {Hydrogen embrittlement, LIST, SEM, SSRT, TEM}, - pages = {21603--21616}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VCCIG5QM\\S0360319918331306.html:text/html}, + urldate = {2020-12-08}, + journal = {Nuclear Materials and Energy}, + author = {Shimada, M. and Merrill, B. J.}, + month = aug, + year = {2017}, + keywords = {Tritium, Helium-3, Neutron-irradiation, Plasma facing-components}, + pages = {699--702}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\IPP2S233\\Shimada et Merrill - 2017 - Tritium decay helium-3 effects in tungsten.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DU4YVBFU\\S2352179116302095.html:text/html}, } -@article{heinola_fuel_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Fuel retention in {JET} {ITER}-{Like} {Wall} from post-mortem analysis}, - volume = {463}, +@article{shah_brittle-ductile_2020, + title = {Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load}, + volume = {541}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514010514}, - doi = {10.1016/j.jnucmat.2014.12.098}, - abstract = {Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311520310242}, + doi = {10.1016/j.jnucmat.2020.152416}, + abstract = {The lifetime of tungsten (W) monoblocks under fusion conditions is ambivalent. In this work, the microstructure dependent mechanical behaviour of pulsed high heat flux (HHF) exposed W monoblock is investigated. Two different microstructural states, i.e. initial (deformed) and recrystallized, both machined from HHF exposed monoblocks are tested using tensile and small punch tests. The initial microstructural state reveals a higher fraction of low angle boundaries along with a preferred orientation of crystals. Following HHF exposure, the recrystallized state exhibits weakening of initial texture along with a higher fraction of high angle boundaries. Irrespective of the testing methodology, both the microstructural states display brittle failure for temperatures lower than 400∘C. For higher temperatures ({\textgreater}400∘C), the recrystallized microstructure exhibits more ductile behaviour as compared to the initial state. The observed microstructural state-dependent mechanical behaviour is further discussed in terms of different microstructural features. The estimated brittle-to-ductile transition temperature (BDTT) range is noticed to be lower for the recrystallized state as compared to the initial state. The lower BDTT in the recrystallized state is attributed to the high purity of the W in combination with its low defect density, thereby preventing segregation of impurities at the recrystallized boundaries and the related premature failure. Based on this observation, it is concluded that the common opinion of the aggravation of BDTT in W due to recrystallization is not unerring, and as a matter of fact, recrystallization in W could be instrumental for preventing the self-castellation of the monoblocks.}, language = {en}, - urldate = {2020-06-19}, + urldate = {2020-12-07}, journal = {Journal of Nuclear Materials}, - author = {Heinola, K. and Widdowson, A. and Likonen, J. and Alves, E. and Baron-Wiechec, A. and Barradas, N. and Brezinsek, S. and Catarino, N. and Coad, P. and Koivuranta, S. and Matthews, G. F. and Mayer, M. and Petersson, P.}, - month = aug, - year = {2015}, - pages = {961--965}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VGSI7KGE\\Heinola et al. - 2015 - Fuel retention in JET ITER-Like Wall from post-mor.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UUFQ2E9Z\\S0022311514010514.html:text/html}, + author = {Shah, V. and van Dommelen, J. A. W. and Altstadt, E. and Das, A. and Geers, M. G. D.}, + month = dec, + year = {2020}, + keywords = {Tungsten, Brittle-to-ductile transition temperature (BDTT), High Heat Flux (HHF) exposure, Recrystallization and embrittlement, Tensile and small punch test}, + pages = {152416}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\TG9AT4TN\\Shah et al. - 2020 - Brittle-ductile transition temperature of recrysta.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\UIIRXFBF\\S0022311520310242.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SG5J3FWP\\S0022311520310242.html:text/html}, } -@article{brezinsek_beryllium_2015, - title = {Beryllium migration in {JET} {ITER}-like wall plasmas}, - volume = {55}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F0029-5515%2F55%2F6%2F063021}, - doi = {10.1088/0029-5515/55/6/063021}, - abstract = {JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation to long-term fuel retention. The (i) limiter and the (ii) divertor configurations have been studied in JET-ILW (JET with a Be first wall and W divertor), and compared with those for the former JET-C (JET with carbon-based plasma-facing components (PFCs)). (i) For the limiter configuration, the Be gross erosion at the contact point was determined in situ by spectroscopy as between 4\% (Ein = 35 eV) and more than 100\%, caused by Be self-sputtering (Ein = 200 eV). Chemically assisted physical sputtering via BeD release has been identified to contribute to the effective Be sputtering yield, i.e. at Ein = 75 eV, erosion was enhanced by about 1/3 with respect to the bare physical sputtering case. An effective gross yield of 10\% is on average representative for limiter plasma conditions, whereas a factor of 2 difference between the gross erosion and net erosion, determined by post-mortem analysis, was found. The primary impurity source in the limiter configuration in JET-ILW is only 25\% higher (in weight) than that for the JET-C case. The main fraction of eroded Be stays within the main chamber. (ii) For the divertor configuration, neutral Be and BeD from physically and chemically assisted physical sputtering by charge exchange neutrals and residual ion flux at the recessed wall enter the plasma, ionize and are transported by scrape-off layer flows towards the inner divertor where significant net deposition takes place. The amount of Be eroded at the first wall (21 g) and the Be amount deposited in the inner divertor (28 g) are in fair agreement, though the balancing is as yet incomplete due to the limited analysis of PFCs. The primary impurity source in the JET-ILW is a factor of 5.3 less in comparison with that for JET-C, resulting in lower divertor material deposition, by more than one order of magnitude. Within the divertor, Be performs far fewer re-erosion and transport steps than C due to an energetic threshold for Be sputtering, and inhibits as a result of this the transport to the divertor floor and the pump duct entrance. The target plates in the JET-ILW inner divertor represent at the strike line a permanent net erosion zone, in contrast to the net deposition zone in JET-C with thick carbon deposits on the CFC (carbon-fibre composite) plates. The Be migration identified is consistent with the observed low long-term fuel retention and dust production with the JET-ILW.}, +@article{bakaev_ab_2020, + title = {Ab initio study of the stability of {H}-{He} clusters at lattice defects in tungsten}, + volume = {478}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X20303153}, + doi = {10.1016/j.nimb.2020.06.033}, + abstract = {The interaction of a H-He pair embedded in various types of lattice defects in the bcc tungsten, such as vacancies, tilt grain boundaries, a core of screw and edge dislocations has been studied using ab initio calculations. It is shown that H-vacancy and He-vacancy clusters are weaker traps for He and H single atoms, respectively, as compared to a single vacancy. H or He atom, solely, is strongly attracted to the studied grain boundary interfaces, while the mutual H-He interaction is negligible (close to the interaction in vacuum) if both atoms are placed in the adjacent trapping sites located on the grain boundary. The H-He pair placed in the core of the screw or edge dislocation exhibits the binding energy of {\textasciitilde}0.2–0.3 eV, which is close to the H-He attraction in the bulk W. The ground-state configurations for H-He dimers located in various lattice defects in W were rationalized on the basis of atomic structure visualizations, bond analysis and charge density distributions. The obtained data are discussed in the frame of the thermal desorption spectroscopy results offering a better understanding of the detrapping stages of He and H isotopes under mixed plasma exposure conditions.}, language = {en}, - number = {6}, - urldate = {2020-06-19}, - journal = {Nuclear Fusion}, - author = {Brezinsek, S. and Widdowson, A. and Mayer, M. and Philipps, V. and Baron-Wiechec, P. and Coenen, J. W. and Heinola, K. and Huber, A. and Likonen, J. and Petersson, P. and Rubel, M. and Stamp, M. F. and Borodin, D. and Coad, J. P. and Carrasco, A. G. and Kirschner, A. and Krat, S. and Krieger, K. and Lipschultz, B. and Linsmeier, Ch and Matthews, G. F. and and, K. Schmid}, - month = may, - year = {2015}, - note = {Publisher: IOP Publishing}, - pages = {063021}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S2D74BGM\\Brezinsek et al. - 2015 - Beryllium migration in JET ITER-like wall plasmas.pdf:application/pdf;IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CLQ2QP3H\\Brezinsek et al. - 2015 - Beryllium migration in JET ITER-like wall plasmas.pdf:application/pdf}, + urldate = {2020-12-04}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Bakaev, Alexander and Terentyev, Dmitry and Zhurkin, Evgeny E.}, + month = sep, + year = {2020}, + keywords = {Hydrogen, Tungsten, Grain boundaries, Helium, Dislocations}, + pages = {269--273}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\U83DFHUG\\Bakaev et al. - 2020 - Ab initio study of the stability of H-He clusters .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EJEYFQKI\\S0168583X20303153.html:text/html}, } -@article{brezinsek_fuel_2013, - title = {Fuel retention studies with the {ITER}-{Like} {Wall} in {JET}}, - volume = {53}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F0029-5515%2F53%2F8%2F083023}, - doi = {10.1088/0029-5515/53/8/083023}, - abstract = {JET underwent a transformation from a full carbon-dominated tokamak to a fully metallic device with beryllium in the main chamber and a tungsten divertor. This material combination is foreseen for the activated phase of ITER. The ITER-Like Wall (ILW) experiment at JET shall demonstrate the plasma compatibility with metallic walls and the reduction in fuel retention. We report on a set of experiments (Ip = 2.0 MA, Bt = 2.0–2.4 T, δ = 0.2–0.4) in different confinement and plasma conditions with global gas balance analysis demonstrating a strong reduction in the long-term retention rate by more than a factor of 10 with respect to carbon-wall reference discharges. All experiments are executed in a series of identical plasma discharges in order to achieve maximum plasma duration until the analysis limit of the active gas handling system is reached. The composition analysis shows high purity of the recovered gas, typically 99\% D. For typical L-mode discharges (Paux = 0.5 MW), type III (Paux = 5.0 MW) and type-I ELMy H-mode plasmas (Paux = 12.0 MW) a drop of the deuterium retention rate normalized to the operational time in divertor configuration is measured from 1.27 × 1021, 1.37 × 1021 and 1.97 × 1021 D s−1 down to 4.8 × 1019, 7.2 × 1019 and 16 × 1019 D s−1, respectively. The dynamic retention increases in the limiter phase in comparison with carbon-fibre composite, but also the outgassing after the discharge has risen in the same manner and overcompensates this transient retention. Overall an upper limit of the long-term retention rate of 1.5 × 1020 D s−1 is obtained with the ILW. The observed reduction by one order of magnitude confirms the expected predictions concerning the plasma-facing material change in ITER and is in line with identification of fuel co-deposition with Be as the main mechanism for the residual long-term retention. The reduction widens the operational space without active cleaning in the DT phase in comparison with a full carbon device.}, +@article{ying_recent_2020, + title = {Recent advances in tritium modeling and its implications on tritium management for outer fuel cycle}, + volume = {161}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620304439}, + doi = {10.1016/j.fusengdes.2020.111895}, + abstract = {Recent advances in tritium transport modeling of helium-cooled ceramic breeding blankets systems has shined light into some tritium management issues. A detailed component model accounting for multi-physics, design, and operational features is necessary to provide accurate estimations of tritium permeation rates to the building/environment- a safety and licensing concern for a fusion nuclear reactor. We found that tritium permeation to buildings can be reduced of ∼20 times when H2 is increased from ∼0.2 Pa to 100 Pa in coolant streams due to the effect of H and T co-permeation. Similarly, the practice of adding about 0.1 \% vol of H2 into the helium purge gas to promote tritium release can also reduce permeation from breeding zones to coolant systems. However, high H2 partial pressure in helium purge gas further complicates tritium extraction methodology, and may compromise extraction efficiency. This paper provides a concentrated analysis of tritium management in the He-cooled ceramic blankets with the goal of providing further outer fuel cycle tritium R\&D guidance from an integrated point of view.}, language = {en}, - number = {8}, - urldate = {2020-06-19}, - journal = {Nuclear Fusion}, - author = {Brezinsek, S. and Loarer, T. and Philipps, V. and Esser, H. G. and Grünhagen, S. and Smith, R. and Felton, R. and Banks, J. and Belo, P. and Boboc, A. and Bucalossi, J. and Clever, M. and Coenen, J. W. and Coffey, I. and Devaux, S. and Douai, D. and Freisinger, M. and Frigione, D. and Groth, M. and Huber, A. and Hobirk, J. and Jachmich, S. and Knipe, S. and Krieger, K. and Kruezi, U. and Marsen, S. and Matthews, G. F. and Meigs, A. G. and Nave, F. and Nunes, I. and Neu, R. and Roth, J. and Stamp, M. F. and Vartanian, S. and and, U. Samm}, - month = jul, - year = {2013}, - note = {Publisher: IOP Publishing}, - pages = {083023}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SS6TCKRT\\Brezinsek et al. - 2013 - Fuel retention studies with the ITER-Like Wall in .pdf:application/pdf}, + urldate = {2020-12-04}, + journal = {Fusion Engineering and Design}, + author = {Ying, Alice and Riva, Marco and Ahn, Mu-Young and Moreno, Carlos and Cristescu, Ion}, + month = dec, + year = {2020}, + keywords = {Tritium transport, Tritium management, Test blanket system, Tritium permeation, Tritium extraction systems}, + pages = {111895}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\BU4MRWY2\\Ying et al. - 2020 - Recent advances in tritium modeling and its implic.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EXV8JWIM\\S0920379620304439.html:text/html}, } -@article{t_hoen_strongly_2013, - title = {Strongly {Reduced} {Penetration} of {Atomic} {Deuterium} in {Radiation}-{Damaged} {Tungsten}}, - volume = {111}, - url = {https://link.aps.org/doi/10.1103/PhysRevLett.111.225001}, - doi = {10.1103/PhysRevLett.111.225001}, - abstract = {Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias conditions. We observe that the fraction of deuterium that penetrates is only 10−5–10−7 of the plasma flux and strongly dependent on the local surface temperature. We propose that deuterium does not directly penetrate bulk tungsten but that it thermalizes at the surface, where it forms a protective chemisorbed layer. We find an energy barrier of 1–2 eV between the surface and bulk, causing the influx of deuterium to be low as compared to the number of defects and leading to slow filling of the damaged layer.}, - number = {22}, - urldate = {2020-06-19}, - journal = {Physical Review Letters}, - author = {’t Hoen, M. H. J. and Mayer, M. and Kleyn, A. W. and Zeijlmans van Emmichoven, P. A.}, - month = nov, - year = {2013}, - note = {Publisher: American Physical Society}, - pages = {225001}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Q8JFYISZ\\’t Hoen et al. - 2013 - Strongly Reduced Penetration of Atomic Deuterium i.pdf:application/pdf;APS Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BD3CF85M\\PhysRevLett.111.html:text/html}, +@unpublished{delaporte-mathurin_parametric_nodate, + type = {Submitted to {Nuclear} {Materials} and {Energy}}, + title = {Parametric optimisation based on {TPD} experiments for rapid and efficient identification of hydrogen transport materials properties}, + copyright = {All rights reserved}, + author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, } -@article{guterl_effects_2019, - title = {Effects of surface processes on hydrogen outgassing from metal in desorption experiments}, - volume = {59}, +@article{gilbert_integrated_2012, + title = {An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation}, + volume = {52}, issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Fab280a}, - doi = {10.1088/1741-4326/ab280a}, - abstract = {Effects of surface processes on hydrogen outgassing during desorption experiments are investigated using a standard reaction–diffusion model describing hydrogen transport, retention and desorption in material. Three mechanisms for hydrogen migration and desorption on material surface are considered: hydrogen migration from material bulk to material surface (readsorption), hydrogen migration from material surface to material bulk (reabsorption) and hydrogen desorption from material surface by molecular recombination. Three hydrogen outgassing regimes are identified: (i) recombination-limited outgassing when hydrogen recombination and desorption is fast compared to hydrogen reabsorption and slow compared to hydrogen transport from material bulk onto material surface (ii) reabsorption-limited outgassing when hydrogen recombination and desorption is slow compared to hydrogen reabsorption and when the effective hydrogen recombination and desorption is slow compared to hydrogen transport from material bulk onto material surface (iii) bulk-limited outgassing otherwise. Regimes of hydrogen outgassing from tungsten and beryllium are estimated for various experimental conditions. Analytical expressions of the outgassing flux are then derived for each outgassing regime, and used to characterize TDS spectra obtained in thermal desorption spectroscopy (TDS) experiments. It is shown that TDS spectra in recombination-limited regime are skewed toward high temperature, while TDS spectra in reabsorption-limited and bulk-limited regimes are skewed toward low temperature. Furthermore, the temperature of the desorption peak in TDS spectra is shown to decrease in recombination-limited regime and to increase in reabsorption-limited and bulk-limited regimes as the total amount of hydrogen stored in material increases. Finally, it is observed that the effective hydrogen recombination rate measured in reabsorption-limited permeation experiments may be not be reliably used to model and predict hydrogen retention and recycling from tungsten during plasma operations in tokamak.}, + shorttitle = {An integrated model for materials in a fusion power plant}, + url = {https://doi.org/10.1088%2F0029-5515%2F52%2F8%2F083019}, + doi = {10.1088/0029-5515/52/8/083019}, + abstract = {The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. As well as producing defects, the neutrons bombarding the materials initiate nuclear reactions, leading to transmutation of the elemental atoms. Products of many of these reactions are gases, particularly helium, which can cause swelling and embrittlement of materials. This paper integrates several different computational techniques to produce a comprehensive picture of the response of materials to neutron irradiation, enabling the assessment of structural integrity of components in a fusion power plant. Neutron-transport calculations for a model of the next-step fusion device DEMO reveal the variation in exposure conditions in different components of the vessel, while inventory calculations quantify the associated implications for transmutation and gas production. The helium production rates are then used, in conjunction with a simple model for He-induced grain-boundary embrittlement based on electronic-structure density functional theory calculations, to estimate the timescales for susceptibility to grain-boundary failure in different fusion-relevant materials. There is wide variation in the predicted grain-boundary-failure lifetimes as a function of both microstructure and chemical composition, with some conservative predictions indicating much less than the required lifetime for components in a fusion power plant.}, language = {en}, - number = {9}, - urldate = {2020-06-19}, + number = {8}, + urldate = {2020-11-30}, journal = {Nuclear Fusion}, - author = {Guterl, Jerome and Smirnov, R. D. and Snyder, P.}, + author = {Gilbert, M. R. and Dudarev, S. L. and Zheng, S. and Packer, L. W. and Sublet, J.-Ch}, month = aug, - year = {2019}, + year = {2012}, note = {Publisher: IOP Publishing}, - pages = {096042}, -} - -@article{pecovnik_influence_2019, - title = {Influence of grain size on deuterium transport and retention in self-damaged tungsten}, - volume = {513}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311518307256}, - doi = {10.1016/j.jnucmat.2018.10.026}, - abstract = {The influence of grain size on deuterium transport and retention in tungsten was studied. For this purpose an experiment was carried out on three polycrystalline tungsten samples with different grain sizes and a single crystal sample with surface orientation {\textless}100{\textgreater}. In order to increase deuterium retention and hence the sensitivity for detection, samples were first damaged by high energy W ions. After damaging, the samples were exposed to a flux of deuterium atoms at 600 K for 70 h. During the exposure the depth profile of the retained deuterium was measured by Nuclear Reaction Analysis using a 3He ion beam. After the exposure the samples were also analysed by Thermal Desorption Spectroscopy. A clear difference in the time dependence of deuterium uptake was noticed between different samples. The experimental results were modeled using a rate-equation model. The influence of different grain size was modeled by changing the effective height of the potential barrier for deuterium atoms to enter into the bulk. We managed to successfully describe the transport of deuterium into the bulk of tungsten by reducing the potential barrier for samples with smaller grain sizes while the barrier for the sample with larger grain size was close to the value for the damaged single crystal sample.}, - language = {en}, - urldate = {2020-06-19}, - journal = {Journal of Nuclear Materials}, - author = {Pečovnik, Matic and Markelj, Sabina and Založnik, Anže and Schwarz-Selinger, Thomas}, - month = jan, - year = {2019}, - keywords = {Tungsten, Deuterium retention, Deuterium transport, Grains, NRA}, - pages = {198--208}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U5CJPVJM\\Pečovnik et al. - 2019 - Influence of grain size on deuterium transport and.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WDGY8SZ5\\S0022311518307256.html:text/html}, + pages = {083019}, + file = {Gilbert et al. - 2012 - An integrated model for materials in a fusion powe.pdf:D\:\\Logiciels\\data_zotero\\storage\\ACCAWEYS\\Gilbert et al. - 2012 - An integrated model for materials in a fusion powe.pdf:application/pdf}, } -@article{zaloznik_deuterium_2017, - title = {Deuterium atom loading of self-damaged tungsten at different sample temperatures}, - volume = {496}, +@article{gilbert_neutron-induced_2013, + series = {{FIFTEENTH} {INTERNATIONAL} {CONFERENCE} {ON} {FUSION} {REACTOR} {MATERIALS}}, + title = {Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials}, + volume = {442}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311517306827}, - doi = {10.1016/j.jnucmat.2017.09.003}, - abstract = {The influence of surface parameters on hydrogen isotope atom absorption into tungsten material was studied. For this purpose a series of experiments was performed, exposing tungsten pre-damaged by tungsten ions, the so-called self-damaged W, to low energy deuterium atoms with the flux density of 4.2×1018D/m2s for 121 h. Exposures were performed at four sample temperatures between 450 K and 600 K. Deuterium concentration was measured in situ and in real time during the exposure by nuclear reaction analysis. After the exposure, thermodesorption spectroscopy was performed on the samples. We have modeled the experimental data using a 1-D rate equation model and determined the detrapping energies and values of modeling parameters, which are describing deuterium atom adsorption on the surface of tungsten and migration of atoms from the surface to the bulk of the material. Assuming two adsorption site types, the determined surface adsorption energies are (0.68±0.02)eV and (0.71±0.02)eV and the activation energies for migration from the surface to the bulk are (1.41±0.02)eV and (1.44±0.02)eV, respectively. Modeling a low temperature plasma loading with the derived parameter set reveals that plasma loading experimental data could not be reproduced. We discuss possible reasons for the discrepancy between atom and plasma loading.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311513005886}, + doi = {10.1016/j.jnucmat.2013.03.085}, + abstract = {In a fusion reactor materials will be subjected to significant fluxes of high-energy neutrons. As well as causing radiation damage, the neutrons also initiate nuclear reactions leading to changes in the chemical composition of materials (transmutation). Many of these reactions produce gases, particularly helium, which cause additional swelling and embrittlement of materials. This paper investigates, using a combination of neutron-transport and inventory calculations, the variation in displacements per atom (dpa) and helium production levels as a function of position within the high flux regions of a recent conceptual model for the ‘next-step’ fusion device DEMO. Subsequently, the gas production rates are used to provide revised estimates, based on new density-functional-theory results, for the critical component lifetimes associated with the helium-induced grain-boundary embrittlement of materials. The revised estimates give more optimistic projections for the lifetimes of materials in a fusion power plant compared to a previous study, while at the same time indicating that helium embrittlement remains one of the most significant factors controlling the structural integrity of fusion power plant components.}, language = {en}, - urldate = {2020-06-19}, + number = {1, Supplement 1}, + urldate = {2020-11-30}, journal = {Journal of Nuclear Materials}, - author = {Založnik, Anže and Markelj, Sabina and Schwarz-Selinger, Thomas and Schmid, Klaus}, - month = dec, - year = {2017}, - pages = {1--8}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2JPBL3IT\\Založnik et al. - 2017 - Deuterium atom loading of self-damaged tungsten at.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\63N6MS2G\\S0022311517306827.html:text/html}, + author = {Gilbert, M. R. and Dudarev, S. L. and Nguyen-Manh, D. and Zheng, S. and Packer, L. W. and Sublet, J. -Ch.}, + month = nov, + year = {2013}, + pages = {S755--S760}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\L3U3WSSS\\Gilbert et al. - 2013 - Neutron-induced dpa, transmutations, gas productio.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TL89TGW9\\S0022311513005886.html:text/html}, } -@article{safi_multi-scale_2017, - title = {Multi-scale modelling to relate beryllium surface temperature, deuterium concentration and erosion in fusion reactor environment}, - volume = {50}, - issn = {0022-3727}, - url = {https://doi.org/10.1088%2F1361-6463%2Faa6967}, - doi = {10.1088/1361-6463/aa6967}, - abstract = {Beryllium (Be) has been chosen as the plasma-facing material for the main wall of ITER, the next generation fusion reactor. Identifying the key parameters that determine Be erosion under reactor relevant conditions is vital to predict the ITER plasma-facing component lifetime and viability. To date, a certain prediction of Be erosion, focusing on the effect of two such parameters, surface temperature and D surface content, has not been achieved. In this work, we develop the first multi-scale KMC-MD modeling approach for Be to provide a more accurate database for its erosion, as well as investigating parameters that affect erosion. First, we calculate the complex relationship between surface temperature and D concentration precisely by simulating the time evolution of the system using an object kinetic Monte Carlo (OKMC) technique. These simulations provide a D surface concentration profile for any surface temperature and incoming D energy. We then describe how this profile can be implemented as a starting configuration in molecular dynamics (MD) simulations. We finally use MD simulations to investigate the effect of temperature (300–800 K) and impact energy (10–200 eV) on the erosion of Be due to D plasma irradiations. The results reveal a strong dependency of the D surface content on temperature. Increasing the surface temperature leads to a lower D concentration at the surface, because of the tendency of D atoms to avoid being accommodated in a vacancy, and de-trapping from impurity sites diffuse fast toward bulk. At the next step, total and molecular Be erosion yields due to D irradiations are analyzed using MD simulations. The results show a strong dependency of erosion yields on surface temperature and incoming ion energy. The total Be erosion yield increases with temperature for impact energies up to 100 eV. However, increasing temperature and impact energy results in a lower fraction of Be atoms being sputtered as BeD molecules due to the lower D surface concentrations at higher temperatures. These findings correlate well with different experiments performed at JET and PISCES-B devices.}, +@article{zhou_growth_2019, + title = {The growth and release of helium bubbles near tungsten surface studied with molecular dynamics simulations}, + volume = {455}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X1930446X}, + doi = {10.1016/j.nimb.2019.06.023}, + abstract = {The growth and release processes of helium bubbles near tungsten surface have been investigated by molecular dynamics (MD) simulations. The results indicate that the surface morphologies are dependent on orientation of surfaces. Before bubble rupture occurs, stepped, thin schistose and pyramidal structures are observed on the (1 1 0), (1 0 0) and (1 1 1) surfaces, respectively. When the angle between the normal direction of surface and the sliding direction (〈1 1 1〉 direction) is larger, flatter surface would be formed and the subsequent release process would be more violent. In the bursting process, the release rate of helium and the degree of surface damage are correlated with the surface stacking height before bubble bursts. Unrepaired crack structures have been observed on the (1 1 0) and (1 0 0) surfaces, while a smaller hole on the (1 1 1) surface. The stacking atoms have a tendency to make the surface restore to the bcc structure. At high temperature, the surface pore with radius ∼1 nm can be self-healed from outer to inner by the diffusion of surface atoms, while no recovery is observed in MD time scale when the ratio of He/V in the bubble is high.}, language = {en}, - number = {20}, - urldate = {2020-06-19}, - journal = {Journal of Physics D: Applied Physics}, - author = {Safi, E. and Valles, G. and Lasa, A. and Nordlund, K.}, - month = apr, - year = {2017}, - note = {Publisher: IOP Publishing}, - pages = {204003}, - file = {Version acceptée:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WS9BCQ75\\Safi et al. - 2017 - Multi-scale modelling to relate beryllium surface .pdf:application/pdf}, + urldate = {2020-01-10}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Zhou, Yulu and Yuan, Chiwen and Li, Tao and Tao, Xiaoma and Ouyang, Yifang}, + month = sep, + year = {2019}, + keywords = {Tungsten, Molecular Dynamics, Bursting, Helium bubble, Molecular dynamics simulations, Self-healing, Surface morphology}, + pages = {66--73}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\6QYWAS86\\Zhou et al. - 2019 - The growth and release of helium bubbles near tung.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\H2BYWYR3\\S0168583X1930446X.html:text/html}, } -@article{hodille_retention_2017, - title = {Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach}, - volume = {57}, - issn = {0029-5515}, - shorttitle = {Retention and release of hydrogen isotopes in tungsten plasma-facing components}, - url = {https://doi.org/10.1088%2F1741-4326%2Faa6d24}, - doi = {10.1088/1741-4326/aa6d24}, - abstract = {Fusion fuel retention (trapping) and release (desorption) from plasma-facing components are critical issues for ITER and for any future industrial demonstration reactors such as DEMO. Therefore, understanding the fundamental mechanisms behind the retention of hydrogen isotopes in first wall and divertor materials is necessary. We developed an approach that couples dedicated experimental studies with modelling at all relevant scales, from microscopic elementary steps to macroscopic observables, in order to build a reliable and predictive fusion reactor wall model. This integrated approach is applied to the ITER divertor material (tungsten), and advances in the development of the wall model are presented. An experimental dataset, including focused ion beam scanning electron microscopy, isothermal desorption, temperature programmed desorption, nuclear reaction analysis and Auger electron spectroscopy, is exploited to initialize a macroscopic rate equation wall model. This model includes all elementary steps of modelled experiments: implantation of fusion fuel, fuel diffusion in the bulk or towards the surface, fuel trapping on defects and release of trapped fuel during a thermal excursion of materials. We were able to show that a single-trap-type single-detrapping-energy model is not able to reproduce an extended parameter space study of a polycrystalline sample exhibiting a single desorption peak. It is therefore justified to use density functional theory to guide the initialization of a more complex model. This new model still contains a single type of trap, but includes the density functional theory findings that the detrapping energy varies as a function of the number of hydrogen isotopes bound to the trap. A better agreement of the model with experimental results is obtained when grain boundary defects are included, as is consistent with the polycrystalline nature of the studied sample. Refinement of this grain boundary model is discussed as well as the inclusion in the model of a thin defective oxide layer following the experimental observation of the presence of an oxygen layer on the surface even after annealing to 1300 K.}, +@article{jiangfeng_one-dimensional_2011, + title = {One-dimensional simulation of hydrogen isotopes diffusion in composite materials by {FVM}}, + volume = {36}, + issn = {0360-3199}, + url = {http://www.sciencedirect.com/science/article/pii/S0360319911003570}, + doi = {10.1016/j.ijhydene.2011.02.040}, + abstract = {Tritium diffusion and permeation in construct materials is one of the most important problems in fusion material research. For the tritium concentration evaluation within each sub-system of the fuel cycle of ITER, a finite volume computer program was developed for diffusion analysis of hydrogen isotopes in composite materials. The program calculates hydrogen isotope concentration distributions through composite materials such as tritium permeation barriers as function of the applied boundary conditions. The program can simulate hydrogen isotopes diffusion through single materials and composite materials in one-dimensional and can also make the output visualization. We look forward to making some comparison calculation for the present calculation with TMAP.}, language = {en}, - number = {7}, - urldate = {2020-06-19}, - journal = {Nuclear Fusion}, - author = {Hodille, E. A. and Ghiorghiu, F. and Addab, Y. and Založnik, A. and Minissale, M. and Piazza, Z. and Martin, C. and Angot, T. and Gallais, L. and Barthe, M.-F. and Becquart, C. S. and Markelj, S. and Mougenot, J. and Grisolia, C. and Bisson, R.}, + number = {9}, + urldate = {2020-10-22}, + journal = {International Journal of Hydrogen Energy}, + author = {Jiangfeng, Song and Zhiyong, Huang and Lianxia, Li and Chang'an, Chen and Deli, Luo}, month = may, - year = {2017}, - note = {Publisher: IOP Publishing}, - pages = {076019}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TLYFGCL5\\Hodille et al. - 2017 - Retention and release of hydrogen isotopes in tung.pdf:application/pdf}, + year = {2011}, + keywords = {Diffusion, Composite materials, Finite Volume Method (FVM), Hydrogen isotope}, + pages = {5702--5706}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PVHLIT63\\Jiangfeng et al. - 2011 - One-dimensional simulation of hydrogen isotopes di.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\LBQ9GGTM\\S0360319911003570.html:text/html}, } -@article{schmid_diffusion-trapping_2016, - title = {Diffusion-trapping modelling of hydrogen recycling in tungsten under {ELM}-like heat loads}, - volume = {T167}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F0031-8949%2Ft167%2F1%2F014025}, - doi = {10.1088/0031-8949/T167/1/014025}, - abstract = {The recycling of D ions impinging onto a W divertor surface is a key input parameter into the power and momentum balance at the target boundary during SOL modeling. It is described by the ratio R of the flux of recombining D2 molecules to the non-reflected incident ion flux. In steady-state plasmas where the surface is in equilibrium with the incident flux, R equals one due to particle conservation. However, during transient events such as edge localized modes (ELMs) the evolution of R with time is not straightforward to predict. Therefore, detailed diffusion-trapping calculations were performed taking into account the variations in power influx and particle energy during an ELM. They showed that in contrast to the naive expectation, that the ELM would deplete the surface and subsequently lead to ‘pumping’ (R 1) of the incident flux by the empty surface, R ≈ 1 or even R occurs. This paper will first describe how the ELM was approximated in the 1D diffusion-trapping code and then discuss the evolution of R during an ELM and in the inter ELM phase. Also, an analytical picture of R will be developed which allows qualitatively understanding the evolution of R as calculated by the diffusion-trapping code.}, +@article{elmukashfi_modelling_2020, + title = {A modelling framework for coupled hydrogen diffusion and mechanical behaviour of engineering components}, + volume = {66}, + issn = {1432-0924}, + url = {https://doi.org/10.1007/s00466-020-01847-9}, + doi = {10.1007/s00466-020-01847-9}, + abstract = {In this paper, we propose a finite element formulation for solving coupled mechanical/diffusion problems. In particular, we study hydrogen diffusion in metals and its impact on their mechanical behaviour (i.e. hydrogen embrittlement). The formulation can be used to model hydrogen diffusion through a material and its accumulation within different microstructural features of the material (dislocations, precipitates, interfaces, etc.). Further, the effect of hydrogen on the plastic response and cohesive strength of different interfaces can be incorporated. The formulation adopts a standard Galerkin method in the discretisation of both the diffusion and mechanical equilibrium equations. Thus, a displacement-based finite element formulation with chemical potential as an additional degree of freedom, rather than the concentration, is employed. Consequently, the diffusion equation can be expressed fundamentally in terms of the gradient in chemical potential, which reduces the continuity requirements on the shape functions to zero degree, \$\$\{{\textbackslash}mathcal \{C\}\}\_\{0\}\$\$C0, i.e. linear functions, compared to the \$\$\{{\textbackslash}mathcal \{C\}\}\_\{1\}\$\$C1continuity condition required when concentration is adopted. Additionally, a consistent interface element formulation can be achieved due to the continuity of the chemical potential across the interface—concentration can be discontinuous at an interface which can lead to numerical problems. As a result, the coding of the FE equations is more straightforward. The details of the physical problem, the finite element formulation and constitutive models are initially discussed. Numerical results for various example problems are then presented, in which the efficiency and accuracy of the proposed formulation are explored and a comparison with the concentration-based formulations is presented.}, language = {en}, - urldate = {2020-06-19}, - journal = {Physica Scripta}, - author = {Schmid, K.}, - month = jan, - year = {2016}, - note = {Publisher: IOP Publishing}, - pages = {014025}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\N9T7TYNS\\Schmid - 2016 - Diffusion-trapping modelling of hydrogen recycling.pdf:application/pdf}, + number = {1}, + urldate = {2020-10-22}, + journal = {Computational Mechanics}, + author = {Elmukashfi, Elsiddig and Tarleton, Edmund and Cocks, Alan C. F.}, + month = jul, + year = {2020}, + pages = {189--220}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\AZWPS2ET\\Elmukashfi et al. - 2020 - A modelling framework for coupled hydrogen diffusi.pdf:application/pdf}, } -@article{hu_predicting_2015, - title = {Predicting hydrogen isotope inventory in plasma-facing components during normal and abnormal operations in fusion devices}, - volume = {465}, +@article{shah_spatially_2020, + title = {Spatially dependent kinetics of helium in tungsten under fusion conditions}, + volume = {535}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311515300702}, - doi = {10.1016/j.jnucmat.2015.06.048}, - abstract = {Hydrogen isotope behavior and inventory in plasma-facing components (PFCs) of fusion devices are key concerns for safe, reliable, and economical operation. To accurately estimate hydrogen isotope retention and recovery in tungsten (the current leading candidate as a PFC), we have developed a model that was recently benchmarked against isotope depth profile and retention level in a tungsten target under various conditions and compared with both experimental data and simulation results. In this research, we have extended the model to include details of transient events. Therefore, one can use this model to estimate hydrogen isotope retention behavior in tungsten and potential other PFC candidates during normal operational pulse, effects of edge-localized modes (ELMs), and a possible cleaning processes scenario.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311519306622}, + doi = {10.1016/j.jnucmat.2020.152104}, + abstract = {Tungsten is the prime candidate material for divertor applications in future nuclear reactors (e.g. ITER and DEMO). In the present work, a spatially dependent cluster dynamics model is developed to investigate and understand the microstructure evolution of tungsten under low energy helium implantation and neutron irradiation varying over bulk length scales of millimetres and irradiation time scales of hours. The diffusion of helium, helium clusters and their trapping at neutron induced defects is simulated along the tungsten monoblock depth. The temperature gradient resulting from a steady state heat load of 10 MWm−2 along the monoblock depth is considered and its influence on the evolution of defects is discussed. The trapping of helium at vacancies and the associated formation of helium-vacancy clusters is found to be pronounced in the sub-surface layers. A significant influence of helium detrapping from grain boundaries and dislocations, along with its resolution from clusters, on the helium diffusion length scales is observed. Additionally, the effect of helium cluster mobility is investigated and overall lower retention in the monoblock bulk is observed through significant release of helium at the surface.}, language = {en}, - urldate = {2020-06-19}, + urldate = {2020-07-22}, journal = {Journal of Nuclear Materials}, - author = {Hu, Alice and Hassanein, Ahmed}, - month = oct, - year = {2015}, - keywords = {ITER, ELMs, Fusion devices, Plasma-facing components, Tritium retention}, - pages = {582--589}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Y44Q5NHY\\S0022311515300702.html:text/html}, + author = {Shah, V. and van Dommelen, J. A. W. and Geers, M. G. D.}, + month = jul, + year = {2020}, + keywords = {Cluster dynamics, Defect diffusion and accumulation, Helium implantation, Helium resolution, Neutron irradiation, Tungsten monoblock}, + pages = {152104}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PP6CQ23Y\\Shah et al. - 2020 - Spatially dependent kinetics of helium in tungsten.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\A8ABU89V\\Shah et al. - 2020 - Spatially dependent kinetics of helium in tungsten.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\56S9H546\\S0022311519306622.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BS4AFSER\\S0022311519306622.html:text/html}, } -@article{bjorkas_variables_2013, - title = {Variables affecting simulated {Be} sputtering yields}, - volume = {439}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311513006363}, - doi = {10.1016/j.jnucmat.2013.04.036}, - abstract = {Since beryllium is a strong candidate for the main plasma-facing material in future fusion reactors, its sputtering behaviour plays an important role in predicting the reactor’s life-time. Consensus about the actual sputtering yields has not yet been achieved, as observations are influenced by experimental method and/or studied sample. In this work, the beryllium sputtering due to deuterium and beryllium self-bombardment is analyzed using molecular dynamics simulations. The main methodological aspects that influence the outcome, such as flux and fluence of the bombardment, are highlighted, and it is shown that the simulated yields also depend on the sample structure and deuterium content.}, +@article{pecovnik_new_2020, + title = {New rate equation model to describe the stabilization of displacement damage by hydrogen atoms during ion irradiation in tungsten}, + volume = {60}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Fab680f}, + doi = {10.1088/1741-4326/ab680f}, + abstract = {The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) during high-energy W-ion irradiation is investigated. For this purpose, we have performed modelling of experimental results where W was sequentially or simultaneously irradiated by 10.8 MeV W ions and exposed to 300 eV D ions. A novel displacement damage creation and stabilization model was newly developed and introduced into the MHIMS-Reservoir (migration of hydrogen isotopes in materials) code. It employs macroscopic rate equations (MREs) for solving the evolution of solute and trapped D concentrations in the material. The new displacement damage creation and stabilization model is based on spontaneous recombination of Frenkel pairs and stabilization of defects that are occupied by D atoms. By using the new model, we could successfully replicate the measured D depth profiles and D thermal desorption data, where a higher defect concentration was observed when D was present during W irradiation as compared to when no D was present. For this we utilized parameters, which include the number of distinct defect types, the de-trapping energies of their fill-levels, their saturation concentrations and their probability for stabilization if they contain a D during the W-ion irradiation. To successfully replicate the experimental results three distinct defect types were needed with several fill-levels. By comparing the de-trapping energies of the defect fill-levels with data available from the literature, the defect types were identified as single-vacancies, small vacancy clusters and large vacancy clusters. The effect of D presence was found to be largest in single vacancies as its concentration increased by about a factor of three, while the concentration of small vacancy clusters increased by about a factor of two. Large vacancy clusters were found to be largely unaffected as they showed very little increase in concentration when D was present.}, language = {en}, - number = {1}, - urldate = {2020-06-19}, - journal = {Journal of Nuclear Materials}, - author = {Björkas, C. and Nordlund, K.}, - month = aug, - year = {2013}, - pages = {174--179}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BKEBN2R2\\S0022311513006363.html:text/html}, + number = {3}, + urldate = {2020-02-26}, + journal = {Nuclear Fusion}, + author = {Pečovnik, M. and Hodille, E. A. and Schwarz-Selinger, T. and Grisolia, C. and Markelj, S.}, + month = feb, + year = {2020}, + pages = {036024}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DMW39L8F\\Pečovnik et al. - 2020 - New rate equation model to describe the stabilizat.pdf:application/pdf;IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YK24AEMX\\Pečovnik et al. - 2020 - New rate equation model to describe the stabilizat.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QGLUF76F\\ab680f.html:text/html}, } -@article{bisson_dynamic_2015, - title = {Dynamic fuel retention in tokamak wall materials: {An} in situ laboratory study of deuterium release from polycrystalline tungsten at room temperature}, - volume = {467}, - issn = {0022-3115}, - shorttitle = {Dynamic fuel retention in tokamak wall materials}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311515301148}, - doi = {10.1016/j.jnucmat.2015.07.028}, - abstract = {Retention of deuterium ion implanted in polycrystalline tungsten samples is studied in situ in an ultra-high vacuum apparatus equipped with a low-flux ion source and a high sensitivity thermo-desorption setup. Retention as a function of ion fluence was measured in the 1017–1021 D+·m−2 range. By combining this new fluence range with the literature in situ experimental data, we evidence the existence of a retention ∝ fluence0.645±0.025 relationship which describes deuterium retention behavior on polycrystalline tungsten on 8 orders of magnitude of fluence. Evolution of deuterium retention as a function of the sample storage time in vacuum at room temperature was followed. A loss of 50\% of the retained deuterium is observed when the storage time is increased from 2 h to 135 h. The role of the surface and of natural bulk defects on the deuterium retention/release in polycrystalline tungsten is discussed in light of the behavior of the single desorption peak obtained with Temperature Programmed Desorption.}, +@article{hou_predictive_2019, + title = {Predictive model of hydrogen trapping and bubbling in nanovoids in bcc metals}, + volume = {18}, + copyright = {2019 The Author(s), under exclusive licence to Springer Nature Limited}, + issn = {1476-4660}, + url = {https://www.nature.com/articles/s41563-019-0422-4}, + doi = {10.1038/s41563-019-0422-4}, + abstract = {The interplay between hydrogen and nanovoids, despite long being recognized as a central factor in hydrogen-induced damage in structural materials, remains poorly understood. Here, focusing on tungsten as a model body-centred cubic system, we explicitly demonstrate sequential adsorption of hydrogen adatoms on Wigner–Seitz squares of nanovoids with distinct energy levels. Interaction between hydrogen adatoms on nanovoid surfaces is shown to be dominated by pairwise power-law repulsion. We establish a predictive model for quantitative determination of the configurations and energetics of hydrogen adatoms in nanovoids. This model, combined with the equation of states of hydrogen gas, enables the prediction of hydrogen molecule formation in nanovoids. Multiscale simulations, performed based on our model, show good agreement with recent thermal desorption experiments. This work clarifies fundamental physics and provides a full-scale predictive model for hydrogen trapping and bubbling in nanovoids, offering long-sought mechanistic insights that are crucial for understanding hydrogen-induced damage in structural materials.}, language = {en}, - urldate = {2020-06-18}, - journal = {Journal of Nuclear Materials}, - author = {Bisson, R. and Markelj, S. and Mourey, O. and Ghiorghiu, F. and Achkasov, K. and Layet, J. -M. and Roubin, P. and Cartry, G. and Grisolia, C. and Angot, T.}, - month = dec, - year = {2015}, - keywords = {Tungsten, Deuterium, Fuel retention, Ion implantation, Plasma surface interaction, Thermodesorption, Tokamak}, - pages = {432--438}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I7QQX76X\\Bisson et al. - 2015 - Dynamic fuel retention in tokamak wall materials .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EBXLLLF4\\S0022311515301148.html:text/html}, -} - -@book{rasmussen_gaussian_2006, - title = {Gaussian {Processes} for {Machine} {Learning}}, - author = {Rasmussen, C. E and Williams, C. K. I.}, - year = {2006}, - file = {Rasmussen et Williams - 2006 - Gaussian Processes for Machine Learning.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\32AWGKG7\\Rasmussen et Williams - 2006 - Gaussian Processes for Machine Learning.pdf:application/pdf}, + number = {8}, + urldate = {2020-10-16}, + journal = {Nature Materials}, + author = {Hou, Jie and Kong, Xiang-Shan and Wu, Xuebang and Song, Jun and Liu, C. S.}, + month = aug, + year = {2019}, + pages = {833--839}, + file = {Hou et al. - 2019 - Predictive model of hydrogen trapping and bubbling.pdf:D\:\\Logiciels\\data_zotero\\storage\\H9W727LI\\Hou et al. - 2019 - Predictive model of hydrogen trapping and bubbling.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\P3PGJKPX\\s41563-019-0422-4.html:text/html}, } -@article{grisolia_plasma_1999, - title = {Plasma wall interaction during long pulse operation in {Tore} {Supra}}, - volume = {266-269}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311598008150}, - doi = {10.1016/S0022-3115(98)00815-0}, - abstract = {Increase of plasma density observed during long pulse operation is reported. The higher the injected and radiated energies are, the faster the increase of density appears. This behaviour correlated with oxygen and hydrogen plasma density increase is attributed to water desorption induced by wall heating due to the high radiated energy of the plasma. These surfaces are far from plasma and are not baked during the conditioning procedures usually used at Tore Supra. Conditioning evidence is seen during discharge series at high injected energy. But this improvement is prevented if disruptions occur in between.}, - language = {en}, - urldate = {2020-06-16}, - journal = {Journal of Nuclear Materials}, - author = {Grisolia, C.}, - month = mar, - year = {1999}, - keywords = {Hydrogen, Carbon, Chemical erosion, Graphite, Ion Bombardment, Oxygen}, - pages = {146--152}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LTDWZ3HT\\S0022311598008150.html:text/html}, +@article{hindmarch_odepack_1982, + title = {{ODEPACK}, {A} {Systematized} {Collection} of {ODE} {Solvers}}, + journal = {Scientific Computing}, + author = {Hindmarch, Alan C.}, + year = {1982}, + pages = {55--64}, + file = {Hindmarch - 1982 - ODEPACK, A Systematized Collection of ODE Solvers.pdf:D\:\\Logiciels\\data_zotero\\storage\\NCWC4WSN\\Hindmarch - 1982 - ODEPACK, A Systematized Collection of ODE Solvers.pdf:application/pdf}, } -@article{raissi_physics_2017, - title = {Physics {Informed} {Deep} {Learning} ({Part} {I}): {Data}-driven {Solutions} of {Nonlinear} {Partial} {Differential} {Equations}}, - shorttitle = {Physics {Informed} {Deep} {Learning} ({Part} {I})}, - url = {http://arxiv.org/abs/1711.10561}, - abstract = {We introduce physics informed neural networks -- neural networks that are trained to solve supervised learning tasks while respecting any given law of physics described by general nonlinear partial differential equations. In this two part treatise, we present our developments in the context of solving two main classes of problems: data-driven solution and data-driven discovery of partial differential equations. Depending on the nature and arrangement of the available data, we devise two distinct classes of algorithms, namely continuous time and discrete time models. The resulting neural networks form a new class of data-efficient universal function approximators that naturally encode any underlying physical laws as prior information. In this first part, we demonstrate how these networks can be used to infer solutions to partial differential equations, and obtain physics-informed surrogate models that are fully differentiable with respect to all input coordinates and free parameters.}, - urldate = {2020-06-15}, - journal = {arXiv:1711.10561 [cs, math, stat]}, - author = {Raissi, Maziar and Perdikaris, Paris and Karniadakis, George Em}, +@article{perrault_safety_2016, + series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, + title = {Safety issues to be taken into account in designing future nuclear fusion facilities}, + volume = {109-111}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379615302994}, + doi = {10.1016/j.fusengdes.2015.10.012}, + abstract = {For several years now, the French “Institut de Radioprotection et de Sûreté Nucléaire” has been carrying out expertise of ITER fusion facility safety files at the request of the French “Autorité de Sûreté Nucléaire”. As part of the lengthy process which should lead to mastering nuclear fusion, different fusion facility projects are currently under study throughout the world to be ready to continue building on the work which will take place in the ITER facility. On the basis of the experience acquired during the ITER safety expertise, the IRSN has carried out a preliminary study of the safety issues which seem necessary to take into account right from the earliest design phase of these DEMO facilities. The issues studied have included the decay heat removal, exposure to ionizing radiation, potential accidents, and effluent releases and waste. The study shows that it will be important to give priority to the following actions, given that their results would have a major influence on the design: assess if decay heat removal is a safety function, re-study the accidents considered in the context of the ITER project and identify those specific to DEMO, and optimize each of the main routes for gaseous tritium releases.}, + language = {en}, + urldate = {2020-10-14}, + journal = {Fusion Engineering and Design}, + author = {Perrault, Didier}, month = nov, - year = {2017}, - note = {arXiv: 1711.10561}, - keywords = {Computer Science - Artificial Intelligence, Computer Science - Machine Learning, Mathematics - Dynamical Systems, Mathematics - Numerical Analysis, Statistics - Machine Learning}, - file = {arXiv.org Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QLM9WJZD\\1711.html:text/html;arXiv Fulltext PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QR2ZZBH2\\Raissi et al. - 2017 - Physics Informed Deep Learning (Part I) Data-driv.pdf:application/pdf}, + year = {2016}, + keywords = {DEMO, Tritium, Safety, Accident, Decay heat, Effluents, safety}, + pages = {1733--1738}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\M6HGGM39\\Perrault - 2016 - Safety issues to be taken into account in designin.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NPYIL4M9\\S0920379615302994.html:text/html}, } -@misc{chris_bowman_c-bowmaninference-tools_2020, - title = {C-bowman/inference-tools: 0.5.3 release}, - shorttitle = {C-bowman/inference-tools}, - url = {https://zenodo.org/record/3757497#.XueCdUUzaUm}, - abstract = {Rather than assuming the mean of the Gaussian process is zero, GpRegressor now treats the mean as a hyper-parameter, and automatically selects a value for the mean which best describes the data. Fixed a bug in the calculation of the derivatives of the log-marginal-likelihood and the log-cross-validation density with respect to the hyper-parameters.}, - urldate = {2020-06-15}, - publisher = {Zenodo}, - author = {Chris Bowman}, - month = apr, - year = {2020}, - doi = {10.5281/zenodo.3757497}, - file = {Zenodo Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NV9AGYC4\\3757497.html:text/html}, +@incollection{kirchheim_25_2014, + address = {Oxford}, + title = {25 - {Hydrogen} in {Metals}}, + isbn = {978-0-444-53770-6}, + url = {http://www.sciencedirect.com/science/article/pii/B9780444537706000253}, + abstract = {Hydrogen in metals attracts interest from scientists since many decades. Most of the interesting properties are related to the small size of hydrogen: its interstitial diffusion accompanied by quantum mechanical tunnel transport results in an extraordinary high mobility of hydrogen atoms in materials. For metals, H diffusivity may reach values as known for ions in aqueous solutions. Thus, thermodynamic equilibrium is reached within comparably short times even at room temperature. Therefore, metal–hydrogen systems are often used as model systems to study physical or chemical properties and their change with concentration (see, for example Oates and Flanagan, 1981, 1981a or Pundt and Kirchheim (2006)). In 1937, Lacher (1937) already used Pd–H (Flanagan and Oates, 1981, 1991) to study solute–solute interactions and interpreted it in the framework of a quasi-chemical approach (Lacher, 1937). The quantum mechanical tunneling as a diffusion mechanism also for atoms in solids was first discovered and discussed for hydrogen tunneling in metals (Flynn and Stoneham, 1970; Völk and Alefeld, 1975; Birnbaum and Flynn, 1976). Völk and Alefeld (1978), Zabel and Peisl (1979, 1980), and Steyrer and Peisl (1986) studied hydrogen density modulations that are related to the sample geometry; and Zabel and his colleagues, as published by Miceli et al. (1985), Uher et al. (1987), Song et al. (1996, 2000), and Uher et al. (1987), firstly used metal–hydrogen systems to study the behavior of systems with reduced dimensions and modulated hydrogen affinity. Kirchheim (1988) and colleagues extensively studied metal–hydrogen systems as representative for solute/solvent systems. The high mobility of hydrogen further allows studying the impact of defects that usually annihilate at elevated temperatures, see Gottstein (2001). It was, therefore, suggested to use hydrogen as a probe for defects (Cahn, 1990; Flanagan et al., 2001a, 2001b; Kirchheim, 2004) and perform site energy spectroscopy by gradually increasing the hydrogen chemical potential.}, + language = {en}, + urldate = {2020-10-09}, + booktitle = {Physical {Metallurgy} ({Fifth} {Edition})}, + publisher = {Elsevier}, + author = {Kirchheim, R. and Pundt, A.}, + editor = {Laughlin, David E. and Hono, Kazuhiro}, + month = jan, + year = {2014}, + doi = {10.1016/B978-0-444-53770-6.00025-3}, + keywords = {Accumulative roll bonding (ARB), Amorphous phases, Atomic mobility, Chemical vapor deposition (CVD), Electrochemical deposition (ED), Electromotoric force, Equal channel angular pressing (ECAP), Geometric phase analysis (GPA), Grain boundary, High pressure torsion (HPT), High resolution transmission electron microscopy (HRTEM), Inert gas condensation (IGC), Metallic Materials, Nanocrystalline materials, Nanocrystalline microstructures, Nanostructured materials, Obtain graded nanostructures, Physical vapor deposition (PVD), Plastic deformation, Severe plastic deformation (SPD), Sputter deposition, Synthesis options, Thin film shess}, + pages = {2597--2705}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YC8VQ7T5\\B9780444537706000253.html:text/html}, } -@article{hirai_design_2018, - title = {Design optimization of the {ITER} tungsten divertor vertical targets}, - volume = {127}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379617309596}, - doi = {10.1016/j.fusengdes.2017.12.007}, - abstract = {The shaping of the ITER divertor vertical targets has been refined as a consequence of manufacturing and engineering considerations during the prototype manufacturing activities. In this paper, the optimized ITER divertor design is presented together with design validation by 3D field line tracing calculation and thermo-mechanical analysis by finite element calculations. Furthermore, the reduction of W monoblock armour thickness to 6 mm is also discussed.}, +@article{krom_hydrogen_2000, + title = {Hydrogen trapping models in steel}, + volume = {31}, + issn = {1543-1916}, + url = {https://doi.org/10.1007/s11663-000-0032-0}, + doi = {10.1007/s11663-000-0032-0}, + abstract = {This article describes the role of hydrogen trapping in steel. Trapping increases the solubility of hydrogen and decreases the diffusivity. Traps are characterized by their nature, i.e., reversible or irreversible, saturable or unsaturable. A dislocation core is a saturable, reversible trap, while voids and crack are unsaturable, reversible traps. A trap model based on saturable, reversible traps is developed, which is slightly different from the trap model of McNabb and Foster. In equilibrium, the trap model corresponds to Oriani’s trap model. Kumnick and Johnson found experimentally that the trap density increases as the plastic strain increases. Using their trap data, it is shown that equilibrium between hydrogen in lattice sites and trap sites can be assumed when strain rates are used as in standard tensile tests.}, language = {en}, - urldate = {2020-06-03}, - journal = {Fusion Engineering and Design}, - author = {Hirai, T. and Carpentier-Chouchana, S. and Escourbiac, F. and Panayotis, S. and Durocher, A. and Ferrand, L. and Garcia-Martinez, M. and Gunn, J. P. and Komarov, V. and Merola, M. and Pitts, R. A. and De Temmerman, G.}, - month = feb, - year = {2018}, - keywords = {Tungsten, Divertor, ITER, High heat flux, Leading edge, Monoblock}, - pages = {66--72}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5N56PMAR\\Hirai et al. - 2018 - Design optimization of the ITER tungsten divertor .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HF8X8DKF\\S0920379617309596.html:text/html}, + number = {6}, + urldate = {2020-10-09}, + journal = {Metallurgical and Materials Transactions B}, + author = {Krom, Alfons H. M. and Bakker, Ad}, + month = dec, + year = {2000}, + pages = {1475--1482}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3CM9W6NN\\Krom et Bakker - 2000 - Hydrogen trapping models in steel.pdf:application/pdf}, } -@article{bonnin_presentation_2016, - title = {Presentation of the {New} {SOLPS}-{ITER} {Code} {Package} for {Tokamak} {Plasma} {Edge} {Modelling}}, - volume = {11}, - doi = {10.1585/pfr.11.1403102}, - abstract = {We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas in the edge region of fusion devices. This package brings together previously existing SOLPS implementations and aims to become the new standard SOLPS version. We summarize the benchmarking work done to ensure backward compatibility with previous work, with a strong requirement on maintaining the viability and usability of the already extensive database of SOLPS runs used for the ITER divertor design and edge plasma physics studies worldwide over the years. The SOLPS-ITER package includes not only the plasma (B2.5) and neutral (Eirene) transport solvers, but also a large set of software tools for input file build-up, conversion of old runs, inline run analysis, and post-processing, all within a standardized portable run environment and version control system. Ongoing and planned upgrades to the code, such as extending the computational domain to the full vacuum vessel wall and a new graphical user interface, are also discussed.}, - journal = {Plasma and Fusion Research}, - author = {Bonnin, Xavier and Dekeyser, Wouter and Pitts, Richard and Coster, David and Voskoboynikov, Serguey and Wiesen, Sven}, - year = {2016}, - keywords = {B2.5-Eirene, plasma code, plasma edge, plasma modelling, SOLPS-ITER}, - pages = {1403102--1403102}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SK4DMVMV\\Bonnin et al. - 2016 - Presentation of the New SOLPS-ITER Code Package fo.pdf:application/pdf;J-Stage - Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WDBIAHM9\\_article.html:text/html}, +@article{aiello_hydrogen_2002, + title = {Hydrogen {Isotopes} {Permeability} in {Eurofer} 97 {Martensitic} {Steel}}, + volume = {41}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST41-872}, + doi = {10.13182/FST41-872}, + abstract = {In considering structural materials for fusion reactors a detailed understanding of the transport parameters and solubility of hydrogen and its isotopes is an important issue which deal with safety and blanket performance aspects.The experimental activities were focused on the determination of hydrogen/deuterium transport parameters through Eurofer 97 in the temperature range 423+723K using a time dependant permeation technique The hydrogen permeation and diffusivity at room temperature and density of trapping sites were also evaluated using Devanathan’s technique.Hydrogen / deuterium permeation experiments on Eurofer 97 showed a non-negligible decrease in permeability with respect to other fusion oriented martensitic steels, even if it remains about one order of magnitude higher compared with that of austenitic AISI 316L steel.}, + number = {3P2}, + urldate = {2020-10-09}, + journal = {Fusion Science and Technology}, + author = {Aiello, A. and Ricapito, I. and Benamati, G. and Valentini, R.}, + month = may, + year = {2002}, + pages = {872--876}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\IAJK39YH\\FST41-872.html:text/html}, } -@article{gu_quantifying_2018, - title = {Quantifying the effect of hydrogen on dislocation dynamics: {A} three-dimensional discrete dislocation dynamics framework}, - volume = {112}, - issn = {0022-5096}, - shorttitle = {Quantifying the effect of hydrogen on dislocation dynamics}, - url = {http://www.sciencedirect.com/science/article/pii/S0022509617309079}, - doi = {10.1016/j.jmps.2018.01.006}, - abstract = {We present a new framework to quantify the effect of hydrogen on dislocations using large scale three-dimensional (3D) discrete dislocation dynamics (DDD) simulations. In this model, the first order elastic interaction energy associated with the hydrogen-induced volume change is accounted for. The three-dimensional stress tensor induced by hydrogen concentration, which is in equilibrium with respect to the dislocation stress field, is derived using the Eshelby inclusion model, while the hydrogen bulk diffusion is treated as a continuum process. This newly developed framework is utilized to quantify the effect of different hydrogen concentrations on the dynamics of a glide dislocation in the absence of an applied stress field as well as on the spacing between dislocations in an array of parallel edge dislocations. A shielding effect is observed for materials having a large hydrogen diffusion coefficient, with the shield effect leading to the homogenization of the shrinkage process leading to the glide loop maintaining its circular shape, as well as resulting in a decrease in dislocation separation distances in the array of parallel edge dislocations. On the other hand, for materials having a small hydrogen diffusion coefficient, the high hydrogen concentrations around the edge characters of the dislocations act to pin them. Higher stresses are required to be able to unpin the dislocations from the hydrogen clouds surrounding them. Finally, this new framework can open the door for further large scale studies on the effect of hydrogen on the different aspects of dislocation-mediated plasticity in metals. With minor modifications of the current formulations, the framework can also be extended to account for general inclusion-induced stress field in discrete dislocation dynamics simulations.}, +@article{benannoune_numerical_2018, + title = {Numerical simulation of the transient hydrogen trapping process using an analytical approximation of the {McNabb} and {Foster} equation}, + volume = {43}, + issn = {0360-3199}, + url = {http://www.sciencedirect.com/science/article/pii/S0360319918310115}, + doi = {10.1016/j.ijhydene.2018.03.179}, + abstract = {In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures, an analytical solution for the differential equation of trapping kinetics is proposed, as a generalization of the Oriani's equilibrium relationship. This solution has been implemented in the Abaqus finite element software, and validated by comparison with the one-dimensional kinetic MRE Hydrogen Isotope Inventory Processes Code (HIIPC). Last, the results of an application on a 3D structure are presented.}, language = {en}, - urldate = {2020-05-28}, - journal = {Journal of the Mechanics and Physics of Solids}, - author = {Gu, Yejun and El-Awady, Jaafar A.}, - month = mar, + number = {18}, + urldate = {2020-09-30}, + journal = {International Journal of Hydrogen Energy}, + author = {Benannoune, Sofiane and Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, + month = may, year = {2018}, - keywords = {Hydrogen, Diffusion, Discrete dislocation dynamics, Embrittlement}, - pages = {491--507}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CLZFRTAL\\Gu et El-Awady - 2018 - Quantifying the effect of hydrogen on dislocation .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CEFLD9Z6\\S0022509617309079.html:text/html}, + keywords = {Hydrogen diffusion, Abaqus, Finite elements calculations, Kinetic trapping, MRE, User subroutine}, + pages = {9083--9093}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZQFQ7R7S\\S0360319918310115.html:text/html}, } -@article{jang_advanced_2008, - title = {Advanced {Thermal}-{Moisture} {Analogy} {Scheme} for {Anisothermal} {Moisture} {Diffusion} {Problem}}, - volume = {130}, - issn = {1043-7398}, - url = {https://asmedigitalcollection.asme.org/electronicpackaging/article/130/1/011004/455172/Advanced-Thermal-Moisture-Analogy-Scheme-for}, - doi = {10.1115/1.2837521}, - language = {en}, - number = {1}, - urldate = {2020-05-28}, - journal = {Journal of Electronic Packaging}, - author = {Jang, Changsoo and Park, Seungbae and Han, Bongtae and Yoon, Samson}, - month = mar, - year = {2008}, - note = {Publisher: American Society of Mechanical Engineers Digital Collection}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9X6T547N\\Jang et al. - 2008 - Advanced Thermal-Moisture Analogy Scheme for Aniso.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9HTI7RFK\\Advanced-Thermal-Moisture-Analogy-Scheme-for.html:text/html}, +@article{oh_coupled_2010, + title = {Coupled {Analysis} of {Hydrogen} {Transport} using {ABAQUS}}, + volume = {4}, + doi = {10.1299/jmmp.4.908}, + abstract = {This paper describes two user subroutines developed within ABAQUS to simulate coupled hydrogen transport equations. Developed user subroutines incorporate two key features in coupled hydrogen transport equations, such as the hydrostatic stress and plastic strain effects on hydrogen transport, and hydrogen-induced dilatational deformation rate. To validate developed subroutines, present simulation results are compared with published results, showing good agreements for all cases considered.}, + number = {7}, + journal = {Journal of Solid Mechanics and Materials Engineering}, + author = {Oh, Chang-Sik and Kim, Yun-Jae and Yoon, Kee-Bong}, + year = {2010}, + keywords = {ABAQUS, Hydrogen Transport Simulation}, + pages = {908--917}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\54AAJFQY\\Oh et al. - 2010 - Coupled Analysis of Hydrogen Transport using ABAQU.pdf:application/pdf;J-Stage - Snapshot:D\:\\Logiciels\\data_zotero\\storage\\82Z5UY8I\\_article.html:text/html}, } -@article{yoon_moisture_2007, - title = {On {Moisture} {Diffusion} {Modeling} {Using} {Thermal}-{Moisture} {Analogy}}, - volume = {129}, - issn = {1043-7398}, - url = {https://asmedigitalcollection.asme.org/electronicpackaging/article/129/4/421/470212/On-Moisture-Diffusion-Modeling-Using-Thermal}, - doi = {10.1115/1.2804090}, +@article{vasikaran_implementation_2020, + title = {Implementation of a reaction-diffusion process in the {Abaqus} finite element software}, + volume = {21}, + copyright = {© E. Vasikaran et al., published by EDP Sciences 2020}, + issn = {2257-7777, 2257-7750}, + url = {https://www.mechanics-industry.org/articles/meca/abs/2020/05/mi190305/mi190305.html}, + doi = {10.1051/meca/2020010}, + abstract = {To increase the Abaqus software capabilities, we propose a strategy to force the software to activate hidden degrees of freedom and to include extra coupled phenomena. As an illustration, we apply this approach to the simulation of a reaction diffusion process, the Gray-Scott model, which exhibits very complex patterns. Several setups have been considered and compared with available results to analyze the abilities of our strategy and to allow the inclusion of complex phenomena in Abaqus.}, language = {en}, - number = {4}, - urldate = {2020-05-28}, - journal = {Journal of Electronic Packaging}, - author = {Yoon, Samson and Han, Bongtae and Wang, Zhaoyang}, + number = {5}, + urldate = {2020-09-30}, + journal = {Mechanics \& Industry}, + author = {Vasikaran, Elisabeth and Charles, Yann and Gilormini, Pierre}, + year = {2020}, + note = {Number: 5 +Publisher: EDP Sciences}, + pages = {508}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\IG3TQ86U\\Vasikaran et al. - 2020 - Implementation of a reaction-diffusion process in .pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZRA6BK8K\\mi190305.html:text/html}, +} + +@techreport{longhurst_tmap7_2008, + title = {{TMAP7} {User} {Manual}}, + url = {https://www.osti.gov/biblio/952013-tmap7-user-manual}, + abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information}, + language = {English}, + number = {INEEL/EXT-04-02352}, + urldate = {2020-09-20}, + institution = {Idaho National Laboratory (INL)}, + author = {Longhurst, Glen R.}, month = dec, - year = {2007}, - note = {Publisher: American Society of Mechanical Engineers Digital Collection}, - pages = {421--426}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SCD6GFTU\\On-Moisture-Diffusion-Modeling-Using-Thermal.html:text/html}, + year = {2008}, + doi = {10.2172/952013}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\GV8WB3C7\\Longhurst - 2008 - TMAP7 User Manual.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\HE9NG682\\952013-tmap7-user-manual.html:text/html}, } -@article{liu_examination_2016, - title = {An examination on the direct concentration approach to simulating moisture diffusion in a multi-material system}, - volume = {60}, - issn = {0026-2714}, - url = {http://www.sciencedirect.com/science/article/pii/S0026271416300476}, - doi = {10.1016/j.microrel.2016.03.012}, - abstract = {In 2009, Xie et al. proposed a diffusion simulation method called direct concentration approach (DCA), which aimed at solving moisture diffusion problems in electronic packages under a transient temperature environment such as reflow process (“Direct Concentration Approach of Moisture Diffusion and Whole Field Vapor Pressure Modeling for Reflow Process: Part I — Theory and Numerical Implementation,” ASME J. Electron. Packag., 131, p. 031,010). However, our study shows that although the DCA may give reasonably accurate concentration results under several circumstances, its relative error in concentration result can be as high as 10\% in one of our test cases. More importantly, the DCA generally leads to the discontinuity of diffusion flux at the bi-material interface, which means that the result may violate the law of mass conservation. A theoretical derivation based on a one-dimensional (1-D) diffusion case is presented to demonstrate the flaw of the DCA using the finite element formulation.}, - language = {en}, - urldate = {2020-05-28}, - journal = {Microelectronics Reliability}, - author = {Liu, Dapeng and Wang, Jing and Liu, Ruiyang and Park, S. B.}, - month = may, - year = {2016}, - keywords = {Moisture diffusion model, Packaging reliability, Simulation}, - pages = {109--115}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VYFE8HYM\\S0026271416300476.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CGHT7FPM\\Liu et al. - 2016 - An examination on the direct concentration approac.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SZJ5KX7R\\S0026271416300476.html:text/html}, +@article{pacher_impurity_2015, + title = {Impurity seeding in {ITER} {DT} plasmas in a carbon-free environment}, + volume = {463}, + issn = {0022-3115}, + url = {http://adsabs.harvard.edu/abs/2015JNuM..463..591P}, + doi = {10.1016/j.jnucmat.2014.11.104}, + abstract = {Impurity seeding has been studied for a carbon-free divertor configuration in ITER using edge/divertor SOLPS code simulations. For high power DT operation, simulations have been performed for varying throughput, power, pumping speed, impurity seeding concentration and species and the results have been parameterised. With these scalings as boundary conditions, core simulations have determined the operating window for carbon-free, impurity-seeded operation.}, + urldate = {2020-09-16}, + journal = {Journal of Nuclear Materials}, + author = {Pacher, H. D. and Kukushkin, A. S. and Pacher, G. W. and Kotov, V. and Pitts, R. A. and Reiter, D.}, + month = aug, + year = {2015}, + pages = {591--595}, } -@article{ialovega_hydrogen_2020, - title = {Hydrogen trapping in tungsten: impact of helium irradiation and thermal cycling}, - volume = {T171}, - issn = {1402-4896}, - shorttitle = {Hydrogen trapping in tungsten}, - url = {https://doi.org/10.1088%2F1402-4896%2Fab68bd}, - doi = {10.1088/1402-4896/ab68bd}, - abstract = {The impact of helium (He) plasma exposure with He fluxes relevant for ITER and WEST on the near-surface microstructure of polycrystalline tungsten (W) is investigated by coupling transmission electron microscopy (TEM) analysis and thermal desorption spectrometry (TDS) measurements. The samples were exposed in the PSI-2 linear plasma device to 75 eV He ions up to the fluence of 3 × 1023 He m−2 with the surface temperature in the range 1053–1073 K. The obtained He bubbles–enriched W samples are subsequently probed with sequences of low flux and low fluence 250 eV deuterium (D) ion implantations and TDS measurements in an ultra-high-vacuum setup to study the effects of the near-surface morphology changes due to the helium irradiation on fundamental mechanisms of deuterium retention. The results obtained for two different near-surface layer He bubbles morphologies revealed that the effects of He irradiation on D retention in W strongly depend on its subsequent thermal cycling. For annealing below 900 K, deuterium retention is similar to the one measured in pristine W. In contrast, for annealing above 1150 K, deuterium retention in the He bubbles-enriched W is increased 3–8 fold as compared to non-damaged W. Additionally, the deuterium desorption peak shifts from 540 to 450 K. This increase of D trapping in the He bubbles-enriched W annealed above 1150 K is presumably associated with a modification of the near-surface microstructure concurrent with an outgassing of He.}, +@article{barrett_designs_2019, + title = {Designs and technologies for plasma-facing wall protection in {EU} {DEMO}}, + volume = {59}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Fab085b}, + doi = {10.1088/1741-4326/ab085b}, + abstract = {The EU DEMO plasma is almost completely enveloped by large breeding blanket segments for tritium breeding and power extraction. Shaping of the blanket plasma-facing wall in 3D may prove to be essential, but this strategy alone is not sufficient to protect against anticipated transient plasma events. The high heat flux wall-limiter approach used in ITER is not thought to be viable in a tritium self-sufficient power reactor, and so in EU DEMO wall protection using discrete limiters is pursued. Two types of discrete limiter are described in this paper. One is an equatorial port limiter designed to handle the power during the plasma start-up phase, making use of water-cooled tungsten/CuCrZr monoblock technology. The second is the upper limiter, featuring a plasma-facing component designed specifically for extreme transient loading due to a vertical displacement event. The heat flux channelling and thermal barrier features of this design are shown to considerably reduce CuCrZr pipe temperature, and so reduce the likelihood of catastrophic failure. A preliminary neutronic calculation has shown that the impact of these discrete limiters on overall tritium breeding ratio is relatively low.}, language = {en}, - urldate = {2020-05-27}, - journal = {Physica Scripta}, - author = {Ialovega, Mykola and Bernard, Elodie and Bisson, Régis and Martin, Celine and Sakamoto, Ryuichi and Kreter, Arkadi and Hodille, Etienne and Angot, Thierry and Grisolia, Christian}, - month = jan, - year = {2020}, - note = {Publisher: IOP Publishing}, - keywords = {TDS}, - pages = {014066}, - file = {Ialovega et al. - 2020 - Hydrogen trapping in tungsten impact of helium ir.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LZLBYNB8\\Ialovega et al. - 2020 - Hydrogen trapping in tungsten impact of helium ir.pdf:application/pdf}, + number = {5}, + urldate = {2020-09-15}, + journal = {Nuclear Fusion}, + author = {Barrett, T. R. and Chuilon, B. and Kovari, M. and Hernandez, D. Leon and Richiusa, M. L. and Adame, E. Rosa and Tivey, R. and Vizvary, Z. and Xue, Y. and Maviglia, F.}, + month = apr, + year = {2019}, + pages = {056019}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\X7GDM7E9\\Barrett et al. - 2019 - Designs and technologies for plasma-facing wall pr.pdf:application/pdf}, } -@article{xu_transport_2020, - title = {Transport parameters and permeation behavior of hydrogen isotopes in the first wall materials of future fusion reactors}, - volume = {155}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620301113}, - doi = {10.1016/j.fusengdes.2020.111563}, - abstract = {The first wall of a future magnetic fusion device is essentially defined as the plasma-facing surface of the breeding blankets, which is supposed to be subjected to bi-directional hydrogen isotopes permeation: in one direction by edge plasma-driven permeation (PDP) of deuterium as well as tritium into blankets, and in the other direction by breed tritium gas-driven permeation (GDP) into the edge plasma. Deuterium and tritium PDP will complicate the recovery of tritium from the blanket, while tritium GDP will lead to an unwanted increase of particle recycling in the first wall region, which could even affect core confinement performance. Reduced activation ferritic/martensitic (RAFM) steels are widely proposed as candidate structural materials for the blanket of a DEMO reactor, the surface coatings made of tungsten are necessary to protect the plasma-facing wall from sputtering under high-energy particle bombardment. Therefore, the characterization of hydrogen isotopes transport through a multi-layer W + RAFM wall is of crucial importance to evaluate major reactor design issues including tritium retention, particle recycling and breeding feasibility, etc. This paper is intended to provide a review over the transport parameters of hydrogen isotopes in RAFM steels, including permeability, diffusivity, solubility and surface recombination coefficient. In addition, the present research status of hydrogen isotopes permeation and retention behavior of tungsten coated RAFM steels is briefly introduced.}, +@article{salari_code_nodate, + title = {Code {Verification} by the {Method} of {Manufactured} {Solutions}}, + abstract = {A procedure for code Verification by the Method of Manufactured Solutions (MMS) is presented. Although the procedure requires a certain amount of creativity and skill, we show that MMS can be applied to a variety of engineering codes which numerically solve partial differential equations. This is illustrated by detailed examples from computational fluid dynamics. The strength of the MMS procedure is that it can identify any coding mistake that affects the order-of-accuracy of the numerical method. A set of examples which use a blind-test protocol demonstrates the kinds of coding mistakes that can (and cannot) be exposed via the MMS code Verification procedure. The principle advantage of the MMS procedure over traditional methods of code Verification is that code capabilities are tested in full generality. The procedure thus results in a high degree of confidence that all coding mistakes which prevent the equations from being solved correctly have been identified.}, + language = {en}, + author = {Salari, Kambiz and Knupp, Patrick}, + pages = {124}, + file = {Salari et Knupp - Code Verification by the Method of Manufactured Sol.pdf:D\:\\Logiciels\\data_zotero\\storage\\AIP2VDC5\\Salari et Knupp - Code Verification by the Method of Manufactured Sol.pdf:application/pdf}, +} + +@article{yu_understanding_2020, + title = {Understanding hydrogen retention in damaged tungsten using experimentally-guided models of complex multispecies evolution}, + volume = {60}, + issn = {0029-5515, 1741-4326}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab9b3c}, + doi = {10.1088/1741-4326/ab9b3c}, language = {en}, - urldate = {2020-05-26}, - journal = {Fusion Engineering and Design}, - author = {Xu, Yue and Wu, Zuo-Sheng and Luo, Lai-Ma and Zan, Xiang and Zhu, Xiao-Yong and Xu, Qiu and Wu, Yu-Cheng}, - month = jun, + number = {9}, + urldate = {2020-08-07}, + journal = {Nuclear Fusion}, + author = {Yu, Qianran and Simmonds, Michael J. and Doerner, Russ. and Tynan, George R. and Yang, Li and Wirth, Brian D. and Marian, Jaime}, + month = sep, year = {2020}, - keywords = {Deuterium retention, First wall, Hydrogen isotopes permeation, Transport parameters, Tungsten coatings}, - pages = {111563}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SBXMAP84\\Xu et al. - 2020 - Transport parameters and permeation behavior of hy.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4IMQ4RLP\\S0920379620301113.html:text/html}, + pages = {096003}, + file = {Yu et al. - 2020 - Understanding hydrogen retention in damaged tungst.pdf:D\:\\Logiciels\\data_zotero\\storage\\HM8IA4X6\\Yu et al. - 2020 - Understanding hydrogen retention in damaged tungst.pdf:application/pdf}, } -@article{richou_realization_2017, - title = {Realization of high heat flux tungsten monoblock type target with graded interlayer for application to {DEMO} divertor}, - volume = {T170}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F1402-4896%2Faa8b02}, - doi = {10.1088/1402-4896/aa8b02}, - abstract = {The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. In DEMO, divertor targets must survive an environment of high heat fluxes (∼up to 20 MW m−2 during slow transients) and neutron irradiation. One advanced concept for components in monoblock configuration concerns the insertion of a compositionally graded layer between tungsten and CuCrZr instead of the soft copper interlayer. As a first step, a thin graded layer (∼25 μm) was developed. As a second step, a thicker graded layer (∼500 μm), which is actually being developed, will also be inserted to study the compliant role of a macroscopic graded layer. This paper reports the results of cyclic high heat flux loading tests up to 20 MW m−2 and to heat flux higher than 25 MW m−2 that mock-ups equipped with thin graded layer survived without visible damage. First feedback on manufacturing steps is also presented. Moreover, the first results obtained on the development of the thick graded layer and its integration in a monoblock configuration are shown.}, +@article{entler_approximation_2018, + title = {Approximation of the economy of fusion energy}, + volume = {152}, + issn = {0360-5442}, + url = {http://www.sciencedirect.com/science/article/pii/S0360544218305395}, + doi = {10.1016/j.energy.2018.03.130}, + abstract = {Conceptual design activities of the first fusion power plants were launched in recent years with a view to putting them into operation by 2050. Nuclear fusion offers significant benefits in comparison with exploited energy sources, especially limitless fuel reserves, inherent nuclear safety, and negligible impact on the environment. The challenge is a high heat and neutron loading of the fusion reactors nuclear zone. The paper brings the ex-ante economic analysis of the fusion power plant model DEMO2 in terms of the cost of electricity. The model investment and operating costs are presented. The limit sales price of electricity was found using the net present value method. The levelized cost of electricity LCOE method with the inclusion of external costs is used for a comparison of selected power plant types based on the OECD statistical data and the EU ExternE project results. The comparison shows the levelized cost of electricity of fusion power plants competitive to the actual renewable resources. After internalisation of external costs, the fusion power plants should become even the second cheapest power source.}, language = {en}, - urldate = {2020-05-25}, - journal = {Physica Scripta}, - author = {Richou, M. and Gallay, F. and Böswirth, B. and Chu, I. and Lenci, M. and Loewenhoff, Th and Quet, A. and Greuner, H. and Kermouche, G. and Meillot, E. and Pintsuk, G. and Visca, E. and You, J. H.}, - month = oct, - year = {2017}, - note = {Publisher: IOP Publishing}, - pages = {014022}, + urldate = {2020-07-28}, + journal = {Energy}, + author = {Entler, Slavomir and Horacek, Jan and Dlouhy, Tomas and Dostal, Vaclav}, + month = jun, + year = {2018}, + keywords = {Economy, External costs, Fusion energy, LCOE, NPV, Nuclear fusion}, + pages = {489--497}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MAJBXBC4\\Entler et al. - 2018 - Approximation of the economy of fusion energy.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ALF6VMWR\\S0360544218305395.html:text/html}, } -@inproceedings{ahrens_paraview_2005, - title = {{ParaView}: {An} {End}-{User} {Tool} for {Large}-{Data} {Visualization}}, - shorttitle = {{ParaView}}, - doi = {10.1016/B978-012387582-2/50038-1}, - abstract = {This chapter describes the design and features of a visualization tool called ParaView, a tool that allows scientists to visualize and analyze extremely large datasets. The tool provides a graphical user interface for the creation and dynamic execution of visualization tasks. ParaView transparently supports the visualization and rendering of large datasets by executing these programs in parallel on shared or distributed memory machines. ParaView supports hardware-accelerated parallel rendering and achieves interactive rendering performance via level-of-detail techniques. The design balances and integrates a number of diverse requirements, including the ability to handle large data, ease of use, and extensibility by developers. The chapter describes the requirements that guided the design, identifies the importance of those requirements to scientific users, and discusses key design decisions and tradeoffs.}, - booktitle = {The {Visualization} {Handbook}}, - author = {Ahrens, James Paul and Geveci, Berk and Law, Charles Chi Wang}, - year = {2005}, +@inproceedings{lassner_tungsten_1999, + title = {Tungsten: {Properties}, {Chemistry}, {Technology} of the {Element}, {Alloys}, and {Chemical} {Compounds}}, + shorttitle = {Tungsten}, + doi = {10.5860/choice.37-2788}, + abstract = {The Element Tungsten: Its Properties. Tungsten History: From Genesis to the 20th Century Products. Important Aspects of Tungsten Chemistry. Tungsten Compounds and Their Application. Industrial Production. Tungsten Alloys. Tungsten and Tungsten Alloy Products. Tungsten in Melting Metallurgy. Tungsten in Hard Metals. Tungsten in Catalysis. Tungsten Scrap Recycling. Ecology. Economy. Tungsten and Living Organisms. Index.}, + author = {Lassner, Erik and Schubert, Wolf-Dieter}, + year = {1999}, + annote = {Reference for tungsten lattice parameter}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SKW8SIQS\\Lassner et Schubert - 1999 - Tungsten Properties, Chemistry, Technology of the.pdf:application/pdf}, } -@article{simmonds_tmap_2020, - title = {{TMAP} modeling of {D} release from baked multi-layer {Be}–{D} co-deposits}, - volume = {T171}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F1402-4896%2Fab4de4}, - doi = {10.1088/1402-4896/ab4de4}, - abstract = {Single-layer Beryllium–Deuterium (Be–D) co-deposits were analyzed using Thermal Desorption mass Spectrometry (TDS) as outlined in the companion paper (Baldwin et al 2019 Phys. Scr. PFMC Proc.). This work details the TMAP modeling and the analysis of selected samples that received double-layer (DL) coatings to study co-deposit thickness and prior bake effects. TDS data were simulated with detrap energies 0.8, 0.9, and 1.0 eV. In DLs formed at 393 K, modeling revealed that under-layers baked at 623 K for either 2 or 20 h had little pumping effect on over-layers, suggesting empty trap removal during bake. Extrapolated to ITER, data and analysis suggest less impact on the ongoing ITER bake efficiency than previously predicted (Baldwin and Doerner 2015 J. Nucl. Mater. 467 38391).}, +@techreport{dolan_assessment_1994, + title = {Assessment of database for interaction of tritium with {ITER} plasma facing materials}, + url = {http://www.osti.gov/servlets/purl/10191406-mAzpKL/webviewable/}, language = {en}, - urldate = {2020-05-11}, - journal = {Physica Scripta}, - author = {Simmonds, M. J. and Baldwin, M. J. and Temmerman, G. De and Doerner, R. P.}, - month = jan, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {014043}, -} - -@article{hunter_matplotlib_2007, - title = {Matplotlib: {A} {2D} {Graphics} {Environment}}, - volume = {9}, - issn = {1558-366X}, - shorttitle = {Matplotlib}, - doi = {10.1109/MCSE.2007.55}, - abstract = {Matplotlib is a 2D graphics package used for Python for application development, interactive scripting,and publication-quality image generation across user interfaces and operating systems}, - number = {3}, - journal = {Computing in Science Engineering}, - author = {Hunter, John D.}, - month = may, - year = {2007}, - note = {Conference Name: Computing in Science Engineering}, - keywords = {2D graphics package, application development, computer graphics, Computer languages, Equations, Graphical user interfaces, Graphics, Image generation, interactive scripting, Interpolation, mathematics computing, Matplotlib, object-oriented programming, operating system, Operating systems, Packaging, Programming profession, publication-quality image generation, Python, scientific programming, scripting languages, software packages, user interface, User interfaces}, - pages = {90--95}, - file = {IEEE Xplore Abstract Record:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U7UCDQY3\\4160265.html:text/html}, + number = {EGG-FSP--11348, 10191406}, + urldate = {2019-11-22}, + author = {Dolan, T.J. and Anderl, R.A.}, + month = sep, + year = {1994}, + doi = {10.2172/10191406}, + pages = {EGG--FSP--11348, 10191406}, + file = {Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:D\:\\Logiciels\\data_zotero\\storage\\A4ED7EDZ\\Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:application/pdf;Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:D\:\\Logiciels\\data_zotero\\storage\\QEFG3RDK\\Dolan et Anderl - 1994 - Assessment of database for interaction of tritium .pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9SKIYWB3\\webviewable.html:text/html}, } -@article{schmid_recent_2017, - title = {Recent progress in the understanding of {H} transport and trapping in {W}}, - volume = {T170}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F1402-4896%2Faa8de0}, - doi = {10.1088/1402-4896/aa8de0}, - abstract = {The retention of hydrogen isotopes (HIs) (H, D and T) in the first, plasma exposed wall is one of the key concerns for the operation of future long pulse fusion devices. It affects the particle-, momentum- and energy balance in the scrape off layer as well as the retention of HIs and their permeation into the coolant. The currently accepted picture that is used for interpreting current laboratory and tokamak experiments is that of diffusion hindered by trapping at lattice defects. This paper summarises recent results that show that this current picture of how HIs are transported and retained in W needs to be extended: the modification of the surface (e.g. blistering) can lead to the formation of fast loss channels for near surface HIs. Trapping at single occupancy traps with fixed de-trapping energy fails to explain isotope exchange experiments, instead a trapping model with multi occupancy traps and fill level dependent de-trapping energies is required. The presence of interstitial impurities like N or C may affect the transport of solute HI. The presence of HIs during damage creation by e.g. neutrons stabilises defects and reduces defect annealing at elevated temperatures.}, +@article{bonny_binding_2014, + title = {On the binding of nanometric hydrogen–helium clusters in tungsten}, + volume = {26}, + issn = {0953-8984}, + url = {https://doi.org/10.1088%2F0953-8984%2F26%2F48%2F485001}, + doi = {10.1088/0953-8984/26/48/485001}, + abstract = {In this work we developed an embedded atom method potential for large scale atomistic simulations in the ternary tungsten–hydrogen–helium (W–H–He) system, focusing on applications in the fusion research domain. Following available ab initio data, the potential reproduces key interactions between H, He and point defects in W and utilizes the most recent potential for matrix W. The potential is applied to assess the thermal stability of various H–He complexes of sizes too large for ab initio techniques. The results show that the dissociation of H–He clusters stabilized by vacancies will occur primarily by emission of hydrogen atoms and then by break-up of V–He complexes, indicating that H–He interaction does influence the release of hydrogen.}, language = {en}, - urldate = {2020-05-05}, - journal = {Physica Scripta}, - author = {Schmid, K. and Bauer, J. and Schwarz-Selinger, T. and Markelj, S. and Toussaint, U. v and Manhard, A. and Jacob, W.}, + number = {48}, + urldate = {2020-07-21}, + journal = {Journal of Physics: Condensed Matter}, + author = {Bonny, G. and Grigorev, P. and Terentyev, D.}, month = oct, - year = {2017}, + year = {2014}, note = {Publisher: IOP Publishing}, - pages = {014037}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BLGHXCG4\\Schmid et al. - 2017 - Recent progress in the understanding of H transpor.pdf:application/pdf}, + pages = {485001}, + file = {Bonny et al. - 2014 - On the binding of nanometric hydrogen–helium clust.pdf:D\:\\Logiciels\\data_zotero\\storage\\Z5E54IB2\\Bonny et al. - 2014 - On the binding of nanometric hydrogen–helium clust.pdf:application/pdf}, } -@book{noauthor_python_2010, - address = {London ; New York}, - title = {Python {Programming} {Fundamentals}}, - isbn = {978-1-84996-536-1}, - abstract = {Computer programming is a skill that can bring great enjoyment from the creativity involved in designing and implementing a solution to a problem. This classroom-tested and easy-to-follow textbook teaches the reader how to program using Python, an accessible language which can be learned incrementally. Through an extensive use of examples and practical exercises, students will learn to recognize and apply abstract patterns in programming, as well as how to inspect the state of a program using a debugger tool. Features: contains numerous examples and solved practice exercises designed for an interactive classroom environment; highlights several patterns which commonly appear in programs, and presents exercises that reinforce recognition and application of these patterns; introduces the use of a debugger, and includes supporting material that reveals how programs work; presents the Tkinter framework for building graphical user interface applications and event-driven programs; provides helpful additional resources for instructors at the associated website: http://cs.luther.edu/{\textasciitilde}leekent/CS1. This hands-on textbook for active learning in the classroom will enable undergraduates in computer science to develop the necessary skills to begin developing their own programs. It employs Python as the introductory language due to the wealth of support available for programmers.}, - language = {Anglais}, - publisher = {Springer London Ltd}, - month = oct, - year = {2010}, - file = {2010 - Python Programming Fundamentals.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BKB9KXUX\\2010 - Python Programming Fundamentals.pdf:application/pdf}, +@article{wang_morphologies_2017, + title = {Morphologies of tungsten nanotendrils grown under helium exposure}, + volume = {7}, + copyright = {2017 The Author(s)}, + issn = {2045-2322}, + url = {https://www.nature.com/articles/srep42315}, + doi = {10.1038/srep42315}, + abstract = {Nanotendril “fuzz” will grow under He bombardment under tokamak-relevant conditions on tungsten plasma-facing materials in a magnetic fusion energy device. We have grown tungsten nanotendrils at low (50 eV) and high (12 keV) He bombardment energy, in the range 900–1000 °C, and characterized them using electron microscopy. Low energy tendrils are finer ({\textasciitilde}22 nm diameter) than high-energy tendrils ({\textasciitilde}176 nm diameter), and low-energy tendrils have a smoother surface than high-energy tendrils. Cavities were omnipresent and typically {\textasciitilde}5–10 nm in size. Oxygen was present at tendril surfaces, but tendrils were all BCC tungsten metal. Electron diffraction measured tendril growth axes and grain boundary angle/axis pairs; no preferential growth axes or angle/axis pairs were observed, and low-energy fuzz grain boundaries tended to be high angle; high energy tendril grain boundaries were not observed. We speculate that the strong tendency to high-angle grain boundaries in the low-energy tendrils implies that as the tendrils twist or bend, strain must accumulate until nucleation of a grain boundary is favorable compared to further lattice rotation. The high-energy tendrils consisted of very large ({\textgreater}100 nm) grains compared to the tendril size, so the nature of the high energy irradiation must enable faster growth with less lattice rotation.}, + language = {en}, + number = {1}, + urldate = {2020-06-29}, + journal = {Scientific Reports}, + author = {Wang, Kun and Doerner, R. P. and Baldwin, M. J. and Meyer, F. W. and Bannister, M. E. and Darbal, Amith and Stroud, Robert and Parish, Chad M.}, + month = feb, + year = {2017}, + note = {Number: 1 +Publisher: Nature Publishing Group}, + pages = {42315}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\T57DCU6G\\Wang et al. - 2017 - Morphologies of tungsten nanotendrils grown under .pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\D9DPCDAF\\srep42315.html:text/html}, } -@book{witelski_methods_2015, - series = {Springer {Undergraduate} {Mathematics} {Series}}, - title = {Methods of {Mathematical} {Modelling}: {Continuous} {Systems} and {Differential} {Equations}}, - isbn = {978-3-319-23041-2}, - shorttitle = {Methods of {Mathematical} {Modelling}}, - url = {https://www.springer.com/gp/book/9783319230412}, - abstract = {This book presents mathematical modelling and the integrated process of formulating sets of equations to describe real-world problems. It describes methods for obtaining solutions of challenging differential equations stemming from problems in areas such as chemical reactions, population dynamics, mechanical systems, and fluid mechanics.Chapters 1 to 4 cover essential topics in ordinary differential equations, transport equations and the calculus of variations that are important for formulating models. Chapters 5 to 11 then develop more advanced techniques including similarity solutions, matched asymptotic expansions, multiple scale analysis, long-wave models, and fast/slow dynamical systems.Methods of Mathematical Modelling will be useful for advanced undergraduate or beginning graduate students in applied mathematics, engineering and other applied sciences.}, +@article{hammond_theoretical_2020, + title = {Theoretical {Model} of {Helium} {Bubble} {Growth} and {Density} in {Plasma}-{Facing} {Metals}}, + volume = {10}, + copyright = {2020 The Author(s)}, + issn = {2045-2322}, + url = {https://www.nature.com/articles/s41598-020-58581-8}, + doi = {10.1038/s41598-020-58581-8}, + abstract = {We present a theoretically-motivated model of helium bubble density as a function of volume for high-pressure helium bubbles in plasma-facing tungsten. The model is a good match to the empirical correlation we published previously [Hammond et al., Acta Mater. 144, 561–578 (2018)] for small bubbles, but the current model uses no adjustable parameters. The model is likely applicable to significantly larger bubbles than the ones examined here, and its assumptions can be extended trivially to other metals and gases. We expect the model to be broadly applicable and useful in coarse-grained models of gas transport in metals.}, language = {en}, - urldate = {2020-05-04}, - publisher = {Springer International Publishing}, - author = {Witelski, Thomas and Bowen, Mark}, - year = {2015}, - doi = {10.1007/978-3-319-23042-9}, - file = {Witelski et Bowen - 2015 - Methods of Mathematical Modelling Continuous Syst.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BMVRPS9M\\Witelski et Bowen - 2015 - Methods of Mathematical Modelling Continuous Syst.pdf:application/pdf}, + number = {1}, + urldate = {2020-06-29}, + journal = {Scientific Reports}, + author = {Hammond, Karl D. and Maroudas, Dimitrios and Wirth, Brian D.}, + month = feb, + year = {2020}, + note = {Number: 1 +Publisher: Nature Publishing Group}, + pages = {2192}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YJ88ABJP\\Hammond et al. - 2020 - Theoretical Model of Helium Bubble Growth and Dens.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QHFTARND\\s41598-020-58581-8.html:text/html}, } -@book{noauthor_introduction_2013, - address = {New York, NY}, - edition = {1st ed. 2014, Corr. 3rd printing 2016}, - title = {Introduction to {Partial} {Differential} {Equations}}, - isbn = {978-3-319-02098-3}, - abstract = {This textbook is designed for a one year course covering the fundamentals of partial differential equations, geared towards advanced undergraduates and beginning graduate students in mathematics, science, engineering, and elsewhere. The exposition carefully balances solution techniques, mathematical rigor, and significant applications, all illustrated by numerous examples. Extensive exercise sets appear at the end of almost every subsection, and include straightforward computational problems to develop and reinforce new techniques and results, details on theoretical developments and proofs, challenging projects both computational and conceptual, and supplementary material that motivates the student to delve further into the subject.No previous experience with the subject of partial differential equations or Fourier theory is assumed, the main prerequisites being undergraduate calculus, both one- and multi-variable, ordinary differential equations, and basic linear algebra. While the classical topics of separation of variables, Fourier analysis, boundary value problems, Green's functions, and special functions continue to form the core of an introductory course, the inclusion of nonlinear equations, shock wave dynamics, symmetry and similarity, the Maximum Principle, financial models, dispersion and solitons, Huygens'. Principle, quantum mechanical systems, and more make this text well attuned to recent developments and trends in this active field of contemporary research. Numerical approximation schemes are an important component of any introductory course, and the text covers the two most basic approaches: finite differences and finite elements.Furthermore, a Solution Manual for instrucors is available by clicking on "Selected Solutions Manual" under the Additional Information section on the right-hand side of this page. Peter J. Olver is professor of mathematics at the University of Minnesota. His wide-ranging research interests are centered on the development of symmetry-based methods for differential equations and their manifold applications. He is the author of over 130 papers published in major scientific research journals as well as 4 other books, including the definitive Springer graduate text, Applications of Lie Groups to Differential Equations, and another undergraduate text, Applied Linear Algebra.}, - language = {Anglais}, - publisher = {Springer International Publishing AG}, - month = nov, - year = {2013}, - file = {2013 - Introduction to Partial Differential Equations.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PFU78NHJ\\2013 - Introduction to Partial Differential Equations.pdf:application/pdf}, +@article{ogorodnikova_deuterium_2011, + title = {Deuterium retention in tungsten exposed to low-energy pure and helium-seeded deuterium plasmas}, + volume = {109}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.3505754}, + doi = {10.1063/1.3505754}, + number = {1}, + urldate = {2020-06-24}, + journal = {Journal of Applied Physics}, + author = {Ogorodnikova, O. V. and Schwarz-Selinger, T. and Sugiyama, K. and Alimov, V. Kh.}, + month = jan, + year = {2011}, + note = {Publisher: American Institute of Physics}, + pages = {013309}, + file = {Ogorodnikova et al. - 2011 - Deuterium retention in tungsten exposed to low-ene.pdf:D\:\\Logiciels\\data_zotero\\storage\\XGV2R2KV\\Ogorodnikova et al. - 2011 - Deuterium retention in tungsten exposed to low-ene.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KEYPVZ2A\\1.html:text/html}, } -@book{borthwick_introduction_2016, - address = {Cham}, - series = {Universitext}, - title = {Introduction to {Partial} {Differential} {Equations}}, - isbn = {978-3-319-48934-6 978-3-319-48936-0}, - url = {http://link.springer.com/10.1007/978-3-319-48936-0}, +@article{alimov_depth_2005, + series = {{PSI}-16}, + title = {Depth distribution of deuterium in single- and polycrystalline tungsten up to depths of several micrometers}, + volume = {337-339}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311504007986}, + doi = {10.1016/j.jnucmat.2004.10.082}, + abstract = {Depth profiles of deuterium trapped in W single crystals and polycrystalline W irradiated with 200eV D ions at 300–323K have been measured up to a depth of 7μm using the D(3He,p)4He nuclear reaction in a resonance-like technique. The proton yield as a function of incident 3He energy was measured and the D depth profile was obtained by deconvolution of the measured proton yields using the program simnra. The depth at which deuterium is retained can be tentatively divided into three zones: (i) the near-surface layer (up to a depth of ∼0.2μm), (ii) the sub-surface layer (from ∼0.5 to ∼2μm), and (iii) the bulk ({\textgreater}5μm). Low-energy D ion irradiation modifies the W structure to depths of up to about 5μm, both for W single crystals and polycrystalline W. Up to this depth trapping sites are created at a fluence of 5×1022/m2 for the retention of deuterium at about 0.1at.\%.}, language = {en}, - urldate = {2020-05-04}, - publisher = {Springer International Publishing}, - author = {Borthwick, David}, - year = {2016}, - doi = {10.1007/978-3-319-48936-0}, - file = {Borthwick - 2016 - Introduction to Partial Differential Equations.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8FPDZ3R2\\Borthwick - 2016 - Introduction to Partial Differential Equations.pdf:application/pdf}, + urldate = {2020-06-23}, + journal = {Journal of Nuclear Materials}, + author = {Alimov, V. Kh. and Roth, J. and Mayer, M.}, + month = mar, + year = {2005}, + keywords = {Tungsten, Deuterium inventory}, + pages = {619--623}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PZGXP4ID\\Alimov et al. - 2005 - Depth distribution of deuterium in single- and pol.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\IGVE89AQ\\S0022311504007986.html:text/html}, } -@article{baldwin_experimental_2014, - title = {Experimental study and modelling of deuterium thermal release from {Be}–{D} co-deposited layers}, - volume = {54}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F0029-5515%2F54%2F7%2F073005}, - doi = {10.1088/0029-5515/54/7/073005}, - abstract = {A study of the thermal desorption of deuterium from 1 µm thick co-deposited Be–(0.1)D layers formed at 330 K by a magnetron sputtering technique is reported. A range of thermal desorption rates 0 ⩽ β ⩽ 1.0 K s−1 are explored with a view to studying the effectiveness of the proposed ITER wall and divertor bake procedure (β = 0 K s−1) to be carried out at 513 and 623 K. Fixed temperature bake durations up to 24 h are examined. The experimental thermal release data are used to validate a model input into the Tritium Migration and Analysis Program (TMAP-7). Good agreement with experiment is observed for a TMAP-7 model incorporating trap populations of activation energies for D release of 0.80 and 0.98 eV, and a dynamically computed surface D atomic to molecular recombination rate.}, +@article{li_review_2020, + title = {A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten}, + issn = {2661-8036}, + url = {https://doi.org/10.1007/s42864-020-00042-w}, + doi = {10.1007/s42864-020-00042-w}, + abstract = {The change in surface damage/microstructures and its effects on the hydrogen (H) isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten (W)-based plasma-facing materials (PFMs) in fusion such as surface erosion, H/He retention and tritium (T) inventory. Complex surface damage/microstructures are introduced in W by high-temperature plasma irradiation and new material design, typically including pre-damage and multi-ion co-deposition induced structures, solute elements and related composites, native defects like dislocations and interfaces, and nanostructures. Systematic experimental and theoretical researches were performed on H isotope/He retention in complex W-based materials in the past decades. In this review, we aim to provide an overview of typical surface damage/microstructures and their effects on H/He retention in W, both in the experiment and multiscale modeling. The distribution/state, dynamics evolution, and interaction with defects/microstructures of H/He are generally summarized at different scales. Finally, the current difficulties, challenges and future directions are also discussed about H/He retention in complex W-based PFMs.}, language = {en}, - number = {7}, - urldate = {2020-04-24}, - journal = {Nuclear Fusion}, - author = {Baldwin, M. J. and Schwarz-Selinger, T. and Doerner, R. P.}, - month = apr, - year = {2014}, - note = {Publisher: IOP Publishing}, - pages = {073005}, - file = {Baldwin et al. - 2014 - Experimental study and modelling of deuterium ther.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\K2KPP4GX\\Baldwin et al. - 2014 - Experimental study and modelling of deuterium ther.pdf:application/pdf}, + urldate = {2020-06-23}, + journal = {Tungsten}, + author = {Li, Yong-Gang and Zheng, Qi-Rong and Wei, Liu-Ming and Zhang, Chuan-Guo and Zeng, Zhi}, + month = jun, + year = {2020}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\9WNJDIMF\\Li et al. - 2020 - A review of surface damagemicrostructures and the.pdf:application/pdf}, } -@book{chen_introduction_2016, - address = {Cham}, - title = {Introduction to {Plasma} {Physics} and {Controlled} {Fusion}}, - isbn = {978-3-319-22309-4}, - url = {https://doi.org/10.1007/978-3-319-22309-4_5}, - abstract = {The third edition of this classic text presents a complete introduction to plasma physics and controlled fusion, written by one of the pioneering scientists in this expanding field. It offers both a simple and intuitive discussion of the basic concepts of the subject matter and an insight into the challenging problems of current research. This outstanding text offers students a painless introduction to this important field; for teachers, a large collection of problems; and for researchers, a concise review of the fundamentals as well as original treatments of a number of topics never before explained so clearly. - -In a wholly lucid manner the second edition covered charged-particle motions, plasmas as fluids, kinetic theory, and nonlinear effects. For the third edition, two new chapters have been added to incorporate discussion of more recent advances in the field. The new chapter 9 on Special Plasmas covers non-neutral plasmas, pure electron plasmas, solid and ultra-cold plasmas, pair-ion plasmas, dusty plasmas, helicon plasmas, atmospheric-pressure plasmas, sheath-bounded plasmas, reconnection and turbulence. Following this, chapter 10 describes Plasma Applications such as magnetic fusion (pinches, mirrors, FRCs, stellarators, tokamaks, spheromaks), plasma accelerators and FELs, ine - -rtial fusion, semiconductor etching, and spacecraft propulsion. -This new revised edition remains an essential text for those new to the field and an invaluable reference source for established researchers.}, +@article{buzi_deuterium_2019, + title = {Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys}, + volume = {21}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179119300584}, + doi = {10.1016/j.nme.2019.100713}, + abstract = {Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.}, language = {en}, - urldate = {2020-04-23}, - publisher = {Springer International Publishing}, - author = {Chen, Francis F.}, - editor = {Chen, Francis F.}, - year = {2016}, - doi = {10.1007/978-3-319-22309-4_5}, - file = {Chen - 2016 - Introduction to Plasma Physics and Controlled Fusi.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TLNRWWFU\\Chen - 2016 - Introduction to Plasma Physics and Controlled Fusi.pdf:application/pdf}, + urldate = {2020-06-23}, + journal = {Nuclear Materials and Energy}, + author = {Buzi, L. and Yeh, M. and Yeh, Y-W. and Donaldson, O. K. and Patino, M. I. and Trelewicz, J. R. and Yao, N. and Doerner, R. and Koel, B. E.}, + month = dec, + year = {2019}, + keywords = {Tungsten, Deuterium, Helium, Plasma-facing materials}, + pages = {100713}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\IFFWVYM6\\Buzi et al. - 2019 - Deuterium and helium ion irradiation of nanograine.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\W9ISQLI3\\S2352179119300584.html:text/html}, } -@article{esteban_hydrogen_2007, - series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, - title = {Hydrogen transport and trapping in {ODS}-{EUROFER}}, - volume = {82}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379607000580}, - doi = {10.1016/j.fusengdes.2007.02.002}, - abstract = {The gas evolution permeation technique has been used to investigate the interaction of hydrogen with the oxide dispersion strengthened (ODS) reduced activation ferritic–martensitic (RAFM) steel EUROFER. The measurements were performed over the temperature range of 420–777K with hydrogen driving pressures ranging from 2.5×103 to 1.0×105Pa. The resultant diffusive transport parameters are a permeability of Φ (molm−1Pa−1/2s−1)=1.22×10−8exp(−34.6(kJmol−1)/RT), a diffusivity of D (m2s−1)=1.33×10−6exp(−30.4(kJmol−1)/RT) and a Sieverts’ constant of Ks (molm−3Pa−1/2)=9.21×10−3exp(−4.2(kJmol−1)/RT). The resultant trapping parameters have been a trap density of Nt=2.0×1025m−3 and trapping energy of Et=44.9kJmol−1. All the hydrogen transport parameters obtained for the ODS-EUROFER are compared to the available data obtained for the base material EUROFER in order to study the influence of the particular micro-structure of ODS in the hydrogen transport. Other RAFM steels of the same kind are included in the comparative analysis. The presence of yttria nanoparticles induces a marked trapping phenomenon and provokes a decrease in the diffusivity and an increase in the solubility of hydrogen in the material at low temperature.}, +@article{dwivedi_hydrogen_2018, + title = {Hydrogen embrittlement in different materials: {A} review}, + volume = {43}, + issn = {0360-3199}, + shorttitle = {Hydrogen embrittlement in different materials}, + url = {http://www.sciencedirect.com/science/article/pii/S0360319918331306}, + doi = {10.1016/j.ijhydene.2018.09.201}, + abstract = {Hydrogen embrittlement (HE) is a widely known phenomenon in high strength materials. HE is responsible for subcritical crack growth in material, fracture initiation and catastrophic failure with subsequent loss in mechanical properties such as ductility, toughness and strength. This hydrogen is induced in the material during electrochemical reaction and high-pressure gaseous hydrogen environment. LIST, SSRT and TDS techniques are performed to know the effect in mechanical properties and amount of hydrogen available in the material. For microstructure examination SEM, FESEM and TEM are performed to know the effect of hydrogen in the internal crystal structure. Also, various mechanisms which are responsible for crack growth and final fracture are discussed. This paper deals with HE definition, mechanisms which causes HE, subcritical crack growth, the concentration of hydrogen measurement and prevention activities are discussed which act as a barrier for hydrogen diffusion.}, language = {en}, - number = {15}, - urldate = {2020-04-21}, - journal = {Fusion Engineering and Design}, - author = {Esteban, G. A. and Peña, A. and Legarda, F. and Lindau, R.}, - month = oct, - year = {2007}, - keywords = {Tritium, Hydrogen, Solubility, Diffusion, Fusion reactor materials}, - pages = {2634--2640}, - file = {Esteban et al. - 2007 - Hydrogen transport and trapping in ODS-EUROFER.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YD4QEDEW\\Esteban et al. - 2007 - Hydrogen transport and trapping in ODS-EUROFER.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U2INAZPR\\S0920379607000580.html:text/html}, + number = {46}, + urldate = {2020-06-19}, + journal = {International Journal of Hydrogen Energy}, + author = {Dwivedi, Sandeep Kumar and Vishwakarma, Manish}, + month = nov, + year = {2018}, + keywords = {Hydrogen embrittlement, LIST, SEM, SSRT, TEM}, + pages = {21603--21616}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VCCIG5QM\\S0360319918331306.html:text/html}, } -@article{virtanen_scipy_2020, - title = {{SciPy} 1.0: fundamental algorithms for scientific computing in {Python}}, - volume = {17}, - copyright = {2020 The Author(s)}, - issn = {1548-7105}, - shorttitle = {{SciPy} 1.0}, - url = {https://www.nature.com/articles/s41592-019-0686-2}, - doi = {10.1038/s41592-019-0686-2}, - abstract = {This Perspective describes the development and capabilities of SciPy 1.0, an open source scientific computing library for the Python programming language.}, +@article{heinola_fuel_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Fuel retention in {JET} {ITER}-{Like} {Wall} from post-mortem analysis}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514010514}, + doi = {10.1016/j.jnucmat.2014.12.098}, + abstract = {Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.}, language = {en}, - number = {3}, - urldate = {2020-04-20}, - journal = {Nature Methods}, - author = {Virtanen, Pauli and Gommers, Ralf and Oliphant, Travis E. and Haberland, Matt and Reddy, Tyler and Cournapeau, David and Burovski, Evgeni and Peterson, Pearu and Weckesser, Warren and Bright, Jonathan and van der Walt, Stéfan J. and Brett, Matthew and Wilson, Joshua and Millman, K. Jarrod and Mayorov, Nikolay and Nelson, Andrew R. J. and Jones, Eric and Kern, Robert and Larson, Eric and Carey, C. J. and Polat, İlhan and Feng, Yu and Moore, Eric W. and VanderPlas, Jake and Laxalde, Denis and Perktold, Josef and Cimrman, Robert and Henriksen, Ian and Quintero, E. A. and Harris, Charles R. and Archibald, Anne M. and Ribeiro, Antônio H. and Pedregosa, Fabian and van Mulbregt, Paul}, - month = mar, - year = {2020}, - note = {Number: 3 -Publisher: Nature Publishing Group}, - pages = {261--272}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CGVWUNFW\\s41592-019-0686-2.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YNACZRNV\\Virtanen et al. - 2020 - SciPy 1.0 fundamental algorithms for scientific c.pdf:application/pdf}, + urldate = {2020-06-19}, + journal = {Journal of Nuclear Materials}, + author = {Heinola, K. and Widdowson, A. and Likonen, J. and Alves, E. and Baron-Wiechec, A. and Barradas, N. and Brezinsek, S. and Catarino, N. and Coad, P. and Koivuranta, S. and Matthews, G. F. and Mayer, M. and Petersson, P.}, + month = aug, + year = {2015}, + pages = {961--965}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\UUFQ2E9Z\\S0022311514010514.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\VGSI7KGE\\Heinola et al. - 2015 - Fuel retention in JET ITER-Like Wall from post-mor.pdf:application/pdf}, } -@article{ishikawa_diffusivity_1986, - title = {The diffusivity of hydrogen in aluminum}, - volume = {34}, - issn = {0001-6160}, - url = {http://www.sciencedirect.com/science/article/pii/0001616086902191}, - doi = {10.1016/0001-6160(86)90219-1}, - abstract = {Using an electrolytic method employing a viscous electrolyte, the diffusivity of hydrogen in aluminum has been measured in the temperature range 285–328 K. The results show that H diffuses by a single-stage process from 285 K up to the melting temperature and no departures from Arrhenius behavior due to trapping effects involving lattice vacancies are observed. -Résumé -Nous avons mesuré la diffusivité de l'hydrogène dans l'aluminium entre 285 et 328 K, par une méthode électrolytique utilisant une électrolyte visqueux. Nos résultats montrent que l'hydrogène diffuse par un mécanisme à stade unique de 285 K jusqu'à la température de fusion; l'on n'observe pas d'écart par rapport à un comportement d'Arrhenius, écart qui serait dû à des effets de piègeage mettant en jeu des lacunes. -Zusammenfassung -Mit einer elektrolytischen Methode wurde die Diffusivität von Wasserstoff in Aluminium im Temperaturbereich zwischen 285 und 328 K in einem viskosen Elektrolyten gemessen. Aus den Ergebnissen folgt, daβ H über einen einstufigen Prozeβ zwischen 285 K und der Schmelztemperatur diffundiert. Abweichungen vom Arrhenius-Verhalten durch Einfangeffekte an Gitterleerstellen werden nicht beobachtet.}, +@article{brezinsek_beryllium_2015, + title = {Beryllium migration in {JET} {ITER}-like wall plasmas}, + volume = {55}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F0029-5515%2F55%2F6%2F063021}, + doi = {10.1088/0029-5515/55/6/063021}, + abstract = {JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation to long-term fuel retention. The (i) limiter and the (ii) divertor configurations have been studied in JET-ILW (JET with a Be first wall and W divertor), and compared with those for the former JET-C (JET with carbon-based plasma-facing components (PFCs)). (i) For the limiter configuration, the Be gross erosion at the contact point was determined in situ by spectroscopy as between 4\% (Ein = 35 eV) and more than 100\%, caused by Be self-sputtering (Ein = 200 eV). Chemically assisted physical sputtering via BeD release has been identified to contribute to the effective Be sputtering yield, i.e. at Ein = 75 eV, erosion was enhanced by about 1/3 with respect to the bare physical sputtering case. An effective gross yield of 10\% is on average representative for limiter plasma conditions, whereas a factor of 2 difference between the gross erosion and net erosion, determined by post-mortem analysis, was found. The primary impurity source in the limiter configuration in JET-ILW is only 25\% higher (in weight) than that for the JET-C case. The main fraction of eroded Be stays within the main chamber. (ii) For the divertor configuration, neutral Be and BeD from physically and chemically assisted physical sputtering by charge exchange neutrals and residual ion flux at the recessed wall enter the plasma, ionize and are transported by scrape-off layer flows towards the inner divertor where significant net deposition takes place. The amount of Be eroded at the first wall (21 g) and the Be amount deposited in the inner divertor (28 g) are in fair agreement, though the balancing is as yet incomplete due to the limited analysis of PFCs. The primary impurity source in the JET-ILW is a factor of 5.3 less in comparison with that for JET-C, resulting in lower divertor material deposition, by more than one order of magnitude. Within the divertor, Be performs far fewer re-erosion and transport steps than C due to an energetic threshold for Be sputtering, and inhibits as a result of this the transport to the divertor floor and the pump duct entrance. The target plates in the JET-ILW inner divertor represent at the strike line a permanent net erosion zone, in contrast to the net deposition zone in JET-C with thick carbon deposits on the CFC (carbon-fibre composite) plates. The Be migration identified is consistent with the observed low long-term fuel retention and dust production with the JET-ILW.}, language = {en}, number = {6}, - urldate = {2020-04-16}, - journal = {Acta Metallurgica}, - author = {Ishikawa, T. and McLellan, R. B.}, - month = jun, - year = {1986}, - pages = {1091--1095}, - file = {Ishikawa et McLellan - 1986 - The diffusivity of hydrogen in aluminum.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5FZ75BFB\\Ishikawa et McLellan - 1986 - The diffusivity of hydrogen in aluminum.pdf:application/pdf}, + urldate = {2020-06-19}, + journal = {Nuclear Fusion}, + author = {Brezinsek, S. and Widdowson, A. and Mayer, M. and Philipps, V. and Baron-Wiechec, P. and Coenen, J. W. and Heinola, K. and Huber, A. and Likonen, J. and Petersson, P. and Rubel, M. and Stamp, M. F. and Borodin, D. and Coad, J. P. and Carrasco, A. G. and Kirschner, A. and Krat, S. and Krieger, K. and Lipschultz, B. and Linsmeier, Ch and Matthews, G. F. and and, K. Schmid}, + month = may, + year = {2015}, + note = {Publisher: IOP Publishing}, + pages = {063021}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\CLQ2QP3H\\Brezinsek et al. - 2015 - Beryllium migration in JET ITER-like wall plasmas.pdf:application/pdf;IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\S2D74BGM\\Brezinsek et al. - 2015 - Beryllium migration in JET ITER-like wall plasmas.pdf:application/pdf}, } -@article{drexler_model-based_2019, - title = {Model-based interpretation of thermal desorption spectra of {Fe}-{C}-{Ti} alloys}, - volume = {789}, - issn = {0925-8388}, - url = {http://www.sciencedirect.com/science/article/pii/S0925838819309090}, - doi = {10.1016/j.jallcom.2019.03.102}, - abstract = {A model-based evaluation procedure by a trap-diffusion integrated finite element model (FEM) is used to interpret the experimentally measured thermal desorption spectra (TDS) of Fe-C-Ti alloys. Two material conditions are compared, i.e. as-quenched vs. quenched and tempered, in which TiC have precipitated. The discrepancy between measurement and simulation is found to be very small for all material conditions. The model shows high trapping energies of around 58 kJ/mol to 110 kJ/mol (0.61 eV–1.14 eV), when the materials are tempered. These traps could be related to carbon vacancies in TiC precipitates.}, +@article{brezinsek_fuel_2013, + title = {Fuel retention studies with the {ITER}-{Like} {Wall} in {JET}}, + volume = {53}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F0029-5515%2F53%2F8%2F083023}, + doi = {10.1088/0029-5515/53/8/083023}, + abstract = {JET underwent a transformation from a full carbon-dominated tokamak to a fully metallic device with beryllium in the main chamber and a tungsten divertor. This material combination is foreseen for the activated phase of ITER. The ITER-Like Wall (ILW) experiment at JET shall demonstrate the plasma compatibility with metallic walls and the reduction in fuel retention. We report on a set of experiments (Ip = 2.0 MA, Bt = 2.0–2.4 T, δ = 0.2–0.4) in different confinement and plasma conditions with global gas balance analysis demonstrating a strong reduction in the long-term retention rate by more than a factor of 10 with respect to carbon-wall reference discharges. All experiments are executed in a series of identical plasma discharges in order to achieve maximum plasma duration until the analysis limit of the active gas handling system is reached. The composition analysis shows high purity of the recovered gas, typically 99\% D. For typical L-mode discharges (Paux = 0.5 MW), type III (Paux = 5.0 MW) and type-I ELMy H-mode plasmas (Paux = 12.0 MW) a drop of the deuterium retention rate normalized to the operational time in divertor configuration is measured from 1.27 × 1021, 1.37 × 1021 and 1.97 × 1021 D s−1 down to 4.8 × 1019, 7.2 × 1019 and 16 × 1019 D s−1, respectively. The dynamic retention increases in the limiter phase in comparison with carbon-fibre composite, but also the outgassing after the discharge has risen in the same manner and overcompensates this transient retention. Overall an upper limit of the long-term retention rate of 1.5 × 1020 D s−1 is obtained with the ILW. The observed reduction by one order of magnitude confirms the expected predictions concerning the plasma-facing material change in ITER and is in line with identification of fuel co-deposition with Be as the main mechanism for the residual long-term retention. The reduction widens the operational space without active cleaning in the DT phase in comparison with a full carbon device.}, language = {en}, - urldate = {2020-04-16}, - journal = {Journal of Alloys and Compounds}, - author = {Drexler, Andreas and Depover, Tom and Verbeken, Kim and Ecker, Werner}, - month = jun, - year = {2019}, - keywords = {A. Alloy, A. Steel, B. Electrochemical calculations, B. Modelling studies, C. Hydrogen embrittlement, C. Stress corrosion}, - pages = {647--657}, - file = {Drexler et al. - 2019 - Model-based interpretation of thermal desorption s.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PVI7D4UC\\Drexler et al. - 2019 - Model-based interpretation of thermal desorption s.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QIMRLR8M\\S0925838819309090.html:text/html}, + number = {8}, + urldate = {2020-06-19}, + journal = {Nuclear Fusion}, + author = {Brezinsek, S. and Loarer, T. and Philipps, V. and Esser, H. G. and Grünhagen, S. and Smith, R. and Felton, R. and Banks, J. and Belo, P. and Boboc, A. and Bucalossi, J. and Clever, M. and Coenen, J. W. and Coffey, I. and Devaux, S. and Douai, D. and Freisinger, M. and Frigione, D. and Groth, M. and Huber, A. and Hobirk, J. and Jachmich, S. and Knipe, S. and Krieger, K. and Kruezi, U. and Marsen, S. and Matthews, G. F. and Meigs, A. G. and Nave, F. and Nunes, I. and Neu, R. and Roth, J. and Stamp, M. F. and Vartanian, S. and and, U. Samm}, + month = jul, + year = {2013}, + note = {Publisher: IOP Publishing}, + pages = {083023}, + file = {Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\SS6TCKRT\\Brezinsek et al. - 2013 - Fuel retention studies with the ITER-Like Wall in .pdf:application/pdf}, } -@article{quiros_blistering_2019, - title = {Blistering and hydrogen retention in poly- and single- crystals of aluminum by a joint experimental-modeling approach}, - volume = {20}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179118301534}, - doi = {10.1016/j.nme.2019.100675}, - abstract = {Aluminum samples have been exposed to a hydrogen plasma generated by a low-pressure – high-density microwave reactor. Aluminum has been chosen as a surrogate for Beryllium. The fluence was kept below 4 × 1024 ions/m2, in order to study the first steps of nucleation and growth of surface and bulk defects, i.e. blisters and bubbles. Experimental analyzes and macroscopic rate equation (MRE) modeling on poly- and single- crystals were made to investigate the role played by grains boundaries in the hydrogen retention. Temperature programmed desorption (TPD) on Al poly-crystals revealed the production of aluminum hydrides (alanes) as majority species in the desorption flux. Comparison of microscopy observations for three different single-crystal orientations (〈100〉, 〈110〉 and 〈111〉) allowed to determine preferential orientations able to attenuate the formation of blisters.}, +@article{t_hoen_strongly_2013, + title = {Strongly {Reduced} {Penetration} of {Atomic} {Deuterium} in {Radiation}-{Damaged} {Tungsten}}, + volume = {111}, + url = {https://link.aps.org/doi/10.1103/PhysRevLett.111.225001}, + doi = {10.1103/PhysRevLett.111.225001}, + abstract = {Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias conditions. We observe that the fraction of deuterium that penetrates is only 10−5–10−7 of the plasma flux and strongly dependent on the local surface temperature. We propose that deuterium does not directly penetrate bulk tungsten but that it thermalizes at the surface, where it forms a protective chemisorbed layer. We find an energy barrier of 1–2 eV between the surface and bulk, causing the influx of deuterium to be low as compared to the number of defects and leading to slow filling of the damaged layer.}, + number = {22}, + urldate = {2020-06-19}, + journal = {Physical Review Letters}, + author = {’t Hoen, M. H. J. and Mayer, M. and Kleyn, A. W. and Zeijlmans van Emmichoven, P. A.}, + month = nov, + year = {2013}, + note = {Publisher: American Physical Society}, + pages = {225001}, + file = {APS Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BD3CF85M\\PhysRevLett.111.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\Q8JFYISZ\\’t Hoen et al. - 2013 - Strongly Reduced Penetration of Atomic Deuterium i.pdf:application/pdf}, +} + +@article{guterl_effects_2019, + title = {Effects of surface processes on hydrogen outgassing from metal in desorption experiments}, + volume = {59}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Fab280a}, + doi = {10.1088/1741-4326/ab280a}, + abstract = {Effects of surface processes on hydrogen outgassing during desorption experiments are investigated using a standard reaction–diffusion model describing hydrogen transport, retention and desorption in material. Three mechanisms for hydrogen migration and desorption on material surface are considered: hydrogen migration from material bulk to material surface (readsorption), hydrogen migration from material surface to material bulk (reabsorption) and hydrogen desorption from material surface by molecular recombination. Three hydrogen outgassing regimes are identified: (i) recombination-limited outgassing when hydrogen recombination and desorption is fast compared to hydrogen reabsorption and slow compared to hydrogen transport from material bulk onto material surface (ii) reabsorption-limited outgassing when hydrogen recombination and desorption is slow compared to hydrogen reabsorption and when the effective hydrogen recombination and desorption is slow compared to hydrogen transport from material bulk onto material surface (iii) bulk-limited outgassing otherwise. Regimes of hydrogen outgassing from tungsten and beryllium are estimated for various experimental conditions. Analytical expressions of the outgassing flux are then derived for each outgassing regime, and used to characterize TDS spectra obtained in thermal desorption spectroscopy (TDS) experiments. It is shown that TDS spectra in recombination-limited regime are skewed toward high temperature, while TDS spectra in reabsorption-limited and bulk-limited regimes are skewed toward low temperature. Furthermore, the temperature of the desorption peak in TDS spectra is shown to decrease in recombination-limited regime and to increase in reabsorption-limited and bulk-limited regimes as the total amount of hydrogen stored in material increases. Finally, it is observed that the effective hydrogen recombination rate measured in reabsorption-limited permeation experiments may be not be reliably used to model and predict hydrogen retention and recycling from tungsten during plasma operations in tokamak.}, language = {en}, - urldate = {2020-04-16}, - journal = {Nuclear Materials and Energy}, - author = {Quiros, C. and Mougenot, J. and Bisson, R. and Redolfi, M. and Michau, A. and Hassouni, K. and Lombardi, G.}, + number = {9}, + urldate = {2020-06-19}, + journal = {Nuclear Fusion}, + author = {Guterl, Jerome and Smirnov, R. D. and Snyder, P.}, month = aug, year = {2019}, - keywords = {Blistering, Aluminum, Hydrogen inventory}, - pages = {100675}, - file = {Quiros et al. - 2019 - Blistering and hydrogen retention in poly- and sin.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UEDLCXEF\\Quiros et al. - 2019 - Blistering and hydrogen retention in poly- and sin.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DT387ZRG\\S2352179118301534.html:text/html}, + note = {Publisher: IOP Publishing}, + pages = {096042}, } -@article{serra_hydrogen_1998, - title = {Hydrogen and deuterium transport and inventory parameters in a {Cu}–0.{65Cr}–0.{08Zr} alloy for fusion reactor applications}, - volume = {258-263}, - issn = {00223115}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0022311598002761}, - doi = {10.1016/S0022-3115(98)00276-1}, - abstract = {A time dependent permeation method has been used to measure the transport and inventory parameters of hydrogen and deuterium in the precipitation hardened (PH) Cu±0.65 wt\% Cr±0.08 wt\% Zr alloy (ELBRODUR HF). The measurements cover the temperature range from 553 to 773 K using a hydrogen or deuterium pressure in the range 1± 100 kPa. The permeabilities, di€usivities and Sieverts' constant values for ELBRODUR obtained in this work were about 2 time higher, 2 times lower and between 3 and 10 time higher respectively to that of Cu (F. Reiter et al., A compilation of Tritium Material Interaction Parameters in Fusion Reactor Materials, EUR 15217 EN (1993)) in the temperature range studied. Using the measured di€usivities and Sieverts' constant values for H2 and D2 and a quantummechanical model, an extrapolation for tritium is also presented. Ó 1998 Elsevier Science B.V. All rights reserved.}, +@article{pecovnik_influence_2019, + title = {Influence of grain size on deuterium transport and retention in self-damaged tungsten}, + volume = {513}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311518307256}, + doi = {10.1016/j.jnucmat.2018.10.026}, + abstract = {The influence of grain size on deuterium transport and retention in tungsten was studied. For this purpose an experiment was carried out on three polycrystalline tungsten samples with different grain sizes and a single crystal sample with surface orientation {\textless}100{\textgreater}. In order to increase deuterium retention and hence the sensitivity for detection, samples were first damaged by high energy W ions. After damaging, the samples were exposed to a flux of deuterium atoms at 600 K for 70 h. During the exposure the depth profile of the retained deuterium was measured by Nuclear Reaction Analysis using a 3He ion beam. After the exposure the samples were also analysed by Thermal Desorption Spectroscopy. A clear difference in the time dependence of deuterium uptake was noticed between different samples. The experimental results were modeled using a rate-equation model. The influence of different grain size was modeled by changing the effective height of the potential barrier for deuterium atoms to enter into the bulk. We managed to successfully describe the transport of deuterium into the bulk of tungsten by reducing the potential barrier for samples with smaller grain sizes while the barrier for the sample with larger grain size was close to the value for the damaged single crystal sample.}, language = {en}, - urldate = {2020-04-16}, + urldate = {2020-06-19}, journal = {Journal of Nuclear Materials}, - author = {Serra, E and Perujo, A}, - month = oct, - year = {1998}, - pages = {1028--1032}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5LM85Y23\\S0022311598002761.html:text/html;Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U6JFAQGI\\Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:application/pdf;Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G96R346E\\Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:application/pdf}, -} - -@article{fernandez_hydrogen_2015, - title = {Hydrogen diffusion and vacancies formation in tungsten: {Density} {Functional} {Theory} calculations and statistical models}, - volume = {94}, - issn = {1359-6454}, - shorttitle = {Hydrogen diffusion and vacancies formation in tungsten}, - url = {http://www.sciencedirect.com/science/article/pii/S1359645415003043}, - doi = {10.1016/j.actamat.2015.04.052}, - abstract = {The interaction of hydrogen with tungsten is investigated by means of the Density Functional Theory (DFT) and statistical methods based on the transition-state theory and thermodynamics. This model yields temperature-dependent data that can help understanding macro-scale experimental results. Within this model, the concentrations of trapped hydrogen atoms at thermodynamic equilibrium are established. Taking into account the configurational entropy, hydrogen is shown to induce vacancy formation below 1000K. Based on this model, TDS spectra are simulated with a basic kinetic model to provide some better insight into the desorption process of hydrogen. Finally, revised mechanisms for hydrogen diffusion in tungsten are proposed; we conclude that the discrepancy existing between the experimental diffusion coefficient measured by Frauenfelder (1969) and the one calculated by DFT would be reconciled provided one uses two different diffusion regimes that would depend on temperature and vacancies concentration.}, - urldate = {2019-10-07}, - journal = {Acta Materialia}, - author = {Fernandez, N. and Ferro, Y. and Kato, D.}, - month = aug, - year = {2015}, - keywords = {Density Functional Theory, DFT, Hydrogen, Nuclear material, Tungsten, Vacancies}, - pages = {307--318}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ICC5AYHS\\Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VQBUYKST\\S1359645415003043.html:text/html;Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UIPYD8RG\\Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:application/pdf}, + author = {Pečovnik, Matic and Markelj, Sabina and Založnik, Anže and Schwarz-Selinger, Thomas}, + month = jan, + year = {2019}, + keywords = {Tungsten, NRA, Deuterium retention, Deuterium transport, Grains}, + pages = {198--208}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\WDGY8SZ5\\S0022311518307256.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\U5CJPVJM\\Pečovnik et al. - 2019 - Influence of grain size on deuterium transport and.pdf:application/pdf}, } -@article{coleman_blueprint_2019, - title = {{BLUEPRINT}: {A} novel approach to fusion reactor design}, - volume = {139}, - issn = {0920-3796}, - shorttitle = {{BLUEPRINT}}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618308019}, - doi = {10.1016/j.fusengdes.2018.12.036}, - abstract = {The European DEMO fusion power reactor (EU-DEMO) is still in the pre-conceptual design phase. The design strategy for the EU-DEMO hinges on investigating multiple reactor designs and technologies in parallel, progressively down-selecting these in the mid-2020s, in preparation for the conceptual design phase. The present implementation of the strategy centres around a baseline single-null design, which is configuration controlled and iterated approximately every two years. The majority of resources are dedicated to studying the baseline design; changing it is expensive, and takes months to do. Competing technologies for different sub-systems (e.g. blankets, magnets) are forced to co-exist within the same physical confines (CAD models), and conform to the same set of performance criteria. Meanwhile, the alternative reactor designs are only loosely defined, with no agreed set of parameters, no CAD models, and no formal framework for study. We argue that the EU-DEMO design strategy is best served by a more efficient implementation methodology which would enable more comprehensive exploration of the DEMO design space. We make the case for a change in approach to the design of DEMO-class reactors in Europe, and propose a solution which bears some resemblance to the present methodology, yet automates and accelerates the sequence of design and analysis activities when generating a design configuration. We present our preliminary attempts to demonstrate the feasibility of our idea, in the form of a new fusion reactor design code: BLUEPRINT. We demonstrate that the typical activities required to generate a DEMO design point can be sped up by four orders of magnitude—from months to minutes—paving the way for a rigorous and broad exploration of the design space.}, - language = {en}, - urldate = {2020-04-15}, - journal = {Fusion Engineering and Design}, - author = {Coleman, M. and McIntosh, S.}, - month = feb, - year = {2019}, - keywords = {DEMO, Design, Fusion reactor, Systems code}, - pages = {26--38}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6J99GRHG\\Coleman et McIntosh - 2019 - BLUEPRINT A novel approach to fusion reactor desi.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D9934YPP\\S0920379618308019.html:text/html}, +@article{zaloznik_deuterium_2017, + title = {Deuterium atom loading of self-damaged tungsten at different sample temperatures}, + volume = {496}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311517306827}, + doi = {10.1016/j.jnucmat.2017.09.003}, + abstract = {The influence of surface parameters on hydrogen isotope atom absorption into tungsten material was studied. For this purpose a series of experiments was performed, exposing tungsten pre-damaged by tungsten ions, the so-called self-damaged W, to low energy deuterium atoms with the flux density of 4.2×1018D/m2s for 121 h. Exposures were performed at four sample temperatures between 450 K and 600 K. Deuterium concentration was measured in situ and in real time during the exposure by nuclear reaction analysis. After the exposure, thermodesorption spectroscopy was performed on the samples. We have modeled the experimental data using a 1-D rate equation model and determined the detrapping energies and values of modeling parameters, which are describing deuterium atom adsorption on the surface of tungsten and migration of atoms from the surface to the bulk of the material. Assuming two adsorption site types, the determined surface adsorption energies are (0.68±0.02)eV and (0.71±0.02)eV and the activation energies for migration from the surface to the bulk are (1.41±0.02)eV and (1.44±0.02)eV, respectively. Modeling a low temperature plasma loading with the derived parameter set reveals that plasma loading experimental data could not be reproduced. We discuss possible reasons for the discrepancy between atom and plasma loading.}, + language = {en}, + urldate = {2020-06-19}, + journal = {Journal of Nuclear Materials}, + author = {Založnik, Anže and Markelj, Sabina and Schwarz-Selinger, Thomas and Schmid, Klaus}, + month = dec, + year = {2017}, + pages = {1--8}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\63N6MS2G\\S0022311517306827.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\2JPBL3IT\\Založnik et al. - 2017 - Deuterium atom loading of self-damaged tungsten at.pdf:application/pdf}, } -@article{roth_tritium_2008, - title = {Tritium inventory in {ITER} plasma-facing materials and tritium removal procedures}, +@article{safi_multi-scale_2017, + title = {Multi-scale modelling to relate beryllium surface temperature, deuterium concentration and erosion in fusion reactor environment}, volume = {50}, - issn = {0741-3335}, - url = {https://doi.org/10.1088%2F0741-3335%2F50%2F10%2F103001}, - doi = {10.1088/0741-3335/50/10/103001}, - abstract = {Interactions between the plasma and the vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining the choice of the plasma-facing materials. A prominent issue in this choice is the tritium inventory build-up in the vessel, which must be limited for safety reasons. The initial material selection, i.e. beryllium (Be) on the main vessel walls, tungsten (W) on the divertor upper baffle and dome, and carbon fibre composite around the strike points on the divertor plates, results both from the attempt to reduce the tritium inventory and to optimize the lifetime of the plasma-facing components.In the framework of the EU Task Force on Plasma–Wall Interaction (PWI TF), the many physics aspects governing the tritium inventory are brought together. Together with supporting information from international experts represented by the ITPA SOL/DIV section, this paper describes the present status of knowledge of the in-vessel tritium inventory build-up. Firstly, the main results from present fusion devices in this field are briefly reviewed. Then, the processes involved are discussed: implantation, trapping and diffusion in plasma-facing materials are considered as well as surface erosion and co-deposition of tritium with eroded material. The intermixing of the different materials and its influence on hydrogen retention and co-deposition is a major source of uncertainty on present estimates and is also addressed.Based on the previous considerations, estimates for the tritium inventory build-up are given for the initial choice of ITER materials, as well as for alternative options. Present estimates indicate a build-up of the tritium inventory to the administrative limit within a few hundred nominal full power D : T discharges, co-deposition with carbon being the dominant process. Therefore, tritium removal methods are also an active area of research within the EU PWI TF, and are discussed. An integrated operational scheme to slow the rate of tritium accumulation is presented, which includes plasma operation as well as conditioning procedures.}, + issn = {0022-3727}, + url = {https://doi.org/10.1088%2F1361-6463%2Faa6967}, + doi = {10.1088/1361-6463/aa6967}, + abstract = {Beryllium (Be) has been chosen as the plasma-facing material for the main wall of ITER, the next generation fusion reactor. Identifying the key parameters that determine Be erosion under reactor relevant conditions is vital to predict the ITER plasma-facing component lifetime and viability. To date, a certain prediction of Be erosion, focusing on the effect of two such parameters, surface temperature and D surface content, has not been achieved. In this work, we develop the first multi-scale KMC-MD modeling approach for Be to provide a more accurate database for its erosion, as well as investigating parameters that affect erosion. First, we calculate the complex relationship between surface temperature and D concentration precisely by simulating the time evolution of the system using an object kinetic Monte Carlo (OKMC) technique. These simulations provide a D surface concentration profile for any surface temperature and incoming D energy. We then describe how this profile can be implemented as a starting configuration in molecular dynamics (MD) simulations. We finally use MD simulations to investigate the effect of temperature (300–800 K) and impact energy (10–200 eV) on the erosion of Be due to D plasma irradiations. The results reveal a strong dependency of the D surface content on temperature. Increasing the surface temperature leads to a lower D concentration at the surface, because of the tendency of D atoms to avoid being accommodated in a vacancy, and de-trapping from impurity sites diffuse fast toward bulk. At the next step, total and molecular Be erosion yields due to D irradiations are analyzed using MD simulations. The results show a strong dependency of erosion yields on surface temperature and incoming ion energy. The total Be erosion yield increases with temperature for impact energies up to 100 eV. However, increasing temperature and impact energy results in a lower fraction of Be atoms being sputtered as BeD molecules due to the lower D surface concentrations at higher temperatures. These findings correlate well with different experiments performed at JET and PISCES-B devices.}, language = {en}, - number = {10}, - urldate = {2020-04-14}, - journal = {Plasma Physics and Controlled Fusion}, - author = {Roth, Joachim and Tsitrone, Emmanuelle and Loarer, Thierry and Philipps, Volker and Brezinsek, Sebastijan and Loarte, Alberto and Counsell, Glenn F. and Doerner, Russell P. and Schmid, Klaus and Ogorodnikova, Olga V. and Causey, Rion A.}, - month = aug, - year = {2008}, + number = {20}, + urldate = {2020-06-19}, + journal = {Journal of Physics D: Applied Physics}, + author = {Safi, E. and Valles, G. and Lasa, A. and Nordlund, K.}, + month = apr, + year = {2017}, note = {Publisher: IOP Publishing}, - pages = {103001}, - file = {Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IIBT4U4N\\Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:application/pdf;Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\V8VT5QFS\\Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:application/pdf}, + pages = {204003}, + file = {Version acceptée:D\:\\Logiciels\\data_zotero\\storage\\WS9BCQ75\\Safi et al. - 2017 - Multi-scale modelling to relate beryllium surface .pdf:application/pdf}, } -@article{hirai_use_2016, - title = {Use of tungsten material for the {ITER} divertor}, - volume = {9}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179115301046}, - doi = {10.1016/j.nme.2016.07.003}, - abstract = {Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R\&D for high performance armor-heat sink joint were necessary to be implemented. In the R\&D, the availability of the technology was demonstrated by high heat flux test of tungsten monoblock components. Not systematically but frequently macro-cracks appeared at the middle of monoblocks after 20MW/m2 loading. The initiation of such macro-cracks was considered to be due to cyclic exposure to high temperature, ∼2000°C, where creep, recrystallization and low cycle fatigue were concerned. To understand correlation between the macro-crack appearance and mechanical properties and possible update of acceptance criteria in the material specification, an activity to characterize the tungsten monoblocks was launched.}, +@article{hodille_retention_2017, + title = {Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach}, + volume = {57}, + issn = {0029-5515}, + shorttitle = {Retention and release of hydrogen isotopes in tungsten plasma-facing components}, + url = {https://doi.org/10.1088%2F1741-4326%2Faa6d24}, + doi = {10.1088/1741-4326/aa6d24}, + abstract = {Fusion fuel retention (trapping) and release (desorption) from plasma-facing components are critical issues for ITER and for any future industrial demonstration reactors such as DEMO. Therefore, understanding the fundamental mechanisms behind the retention of hydrogen isotopes in first wall and divertor materials is necessary. We developed an approach that couples dedicated experimental studies with modelling at all relevant scales, from microscopic elementary steps to macroscopic observables, in order to build a reliable and predictive fusion reactor wall model. This integrated approach is applied to the ITER divertor material (tungsten), and advances in the development of the wall model are presented. An experimental dataset, including focused ion beam scanning electron microscopy, isothermal desorption, temperature programmed desorption, nuclear reaction analysis and Auger electron spectroscopy, is exploited to initialize a macroscopic rate equation wall model. This model includes all elementary steps of modelled experiments: implantation of fusion fuel, fuel diffusion in the bulk or towards the surface, fuel trapping on defects and release of trapped fuel during a thermal excursion of materials. We were able to show that a single-trap-type single-detrapping-energy model is not able to reproduce an extended parameter space study of a polycrystalline sample exhibiting a single desorption peak. It is therefore justified to use density functional theory to guide the initialization of a more complex model. This new model still contains a single type of trap, but includes the density functional theory findings that the detrapping energy varies as a function of the number of hydrogen isotopes bound to the trap. A better agreement of the model with experimental results is obtained when grain boundary defects are included, as is consistent with the polycrystalline nature of the studied sample. Refinement of this grain boundary model is discussed as well as the inclusion in the model of a thin defective oxide layer following the experimental observation of the presence of an oxygen layer on the surface even after annealing to 1300 K.}, language = {en}, - urldate = {2020-04-12}, - journal = {Nuclear Materials and Energy}, - author = {Hirai, T. and Panayotis, S. and Barabash, V. and Amzallag, C. and Escourbiac, F. and Durocher, A. and Merola, M. and Linke, J. and Loewenhoff, Th. and Pintsuk, G. and Wirtz, M. and Uytdenhouwen, I.}, - month = dec, - year = {2016}, - pages = {616--622}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X95BBN5J\\Hirai et al. - 2016 - Use of tungsten material for the ITER divertor.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DUQXP5GH\\S2352179115301046.html:text/html}, + number = {7}, + urldate = {2020-06-19}, + journal = {Nuclear Fusion}, + author = {Hodille, E. A. and Ghiorghiu, F. and Addab, Y. and Založnik, A. and Minissale, M. and Piazza, Z. and Martin, C. and Angot, T. and Gallais, L. and Barthe, M.-F. and Becquart, C. S. and Markelj, S. and Mougenot, J. and Grisolia, C. and Bisson, R.}, + month = may, + year = {2017}, + note = {Publisher: IOP Publishing}, + pages = {076019}, + file = {Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\TLYFGCL5\\Hodille et al. - 2017 - Retention and release of hydrogen isotopes in tung.pdf:application/pdf}, } -@article{hollingsworth_comparative_2019, - title = {Comparative study of deuterium retention in irradiated {Eurofer} and {Fe}–{Cr} from a new ion implantation materials facility}, - volume = {60}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Fab546e}, - doi = {10.1088/1741-4326/ab546e}, - abstract = {A new facility to study the interaction of hydrogen isotopes with nuclear fusion-relevant first wall materials, and their retention and release, has been produced. The new facility allows for implanting a range of gases into samples, including tritium. An accurate study of isotope effects, such as the isotopic exchange in damaged microstructure, has previously been difficult due to a background signal of light hydrogen. This new capability will allow virtually background free measurements using tritium and deuterium. The design and build of this facility are described and commissioning results are presented. Within the UKAEA-led tritium retention in controlled and evolving microstructure (TRiCEM) project, this facility is used for the comparative study of deuterium retention in self-ion irradiated Eurofer steel and Fe–Cr alloy. Self-ion bombardment with energies of 0.5 MeV is used to mimic the defects created by neutrons in fusion power plants and the created traps are then filled with deuterium in the new facility. Implanted samples are analysed using thermal desorption spectrometry (TDS), secondary ion mass spectrometry (SIMS), and transmission electron microscopy. Results on the total deuterium content as a function of time, TDS spectra and SIMS analysis are presented. A comparison of the results for Eurofer and Fe–Cr revealed several differences. While some of them may be due to experimental details like different time delays between exposure and analysis, others, such as deuterium retention as function of dose, might be genuine and require further studies.}, +@article{schmid_diffusion-trapping_2016, + title = {Diffusion-trapping modelling of hydrogen recycling in tungsten under {ELM}-like heat loads}, + volume = {T167}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F0031-8949%2Ft167%2F1%2F014025}, + doi = {10.1088/0031-8949/T167/1/014025}, + abstract = {The recycling of D ions impinging onto a W divertor surface is a key input parameter into the power and momentum balance at the target boundary during SOL modeling. It is described by the ratio R of the flux of recombining D2 molecules to the non-reflected incident ion flux. In steady-state plasmas where the surface is in equilibrium with the incident flux, R equals one due to particle conservation. However, during transient events such as edge localized modes (ELMs) the evolution of R with time is not straightforward to predict. Therefore, detailed diffusion-trapping calculations were performed taking into account the variations in power influx and particle energy during an ELM. They showed that in contrast to the naive expectation, that the ELM would deplete the surface and subsequently lead to ‘pumping’ (R 1) of the incident flux by the empty surface, R ≈ 1 or even R occurs. This paper will first describe how the ELM was approximated in the 1D diffusion-trapping code and then discuss the evolution of R during an ELM and in the inter ELM phase. Also, an analytical picture of R will be developed which allows qualitatively understanding the evolution of R as calculated by the diffusion-trapping code.}, language = {en}, - number = {1}, - urldate = {2020-04-10}, - journal = {Nuclear Fusion}, - author = {Hollingsworth, A. and Lavrentiev, M. Yu and Watkins, R. and Davies, A. C. and Davies, S. and Smith, R. and Mason, D. R. and Baron-Wiechec, A. and Kollo, Z. and Hess, J. and Jepu, I. and Likonen, J. and Heinola, K. and Mizohata, K. and Meslin, E. and Barthe, M.-F. and Widdowson, A. and Grech, I. S. and Abraham, K. and Pender, E. and McShee, A. and Martynova, Y. and Freisinger, M. and Backer, A. De}, - month = nov, - year = {2019}, + urldate = {2020-06-19}, + journal = {Physica Scripta}, + author = {Schmid, K.}, + month = jan, + year = {2016}, note = {Publisher: IOP Publishing}, - pages = {016024}, - file = {Hollingsworth et al. - 2019 - Comparative study of deuterium retention in irradi.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YEXXT4SV\\Hollingsworth et al. - 2019 - Comparative study of deuterium retention in irradi.pdf:application/pdf}, + pages = {014025}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\N9T7TYNS\\Schmid - 2016 - Diffusion-trapping modelling of hydrogen recycling.pdf:application/pdf}, } -@article{ogorodnikova_recombination_2019, - title = {Recombination coefficient of hydrogen on tungsten surface}, - volume = {522}, +@article{hu_predicting_2015, + title = {Predicting hydrogen isotope inventory in plasma-facing components during normal and abnormal operations in fusion devices}, + volume = {465}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311519300030}, - doi = {10.1016/j.jnucmat.2019.05.017}, - abstract = {The recombination coefficient is an important parameter for modelling hydrogen-metal interaction. It is responsible for hydrogen desorption from the surface of the metal and, therefore, significantly affects the hydrogen penetration into the metal, accumulation in and permeation through the metal. In the present work, the recombination coefficient of hydrogen (H) on tungsten (W) surface is examined. It is shown that the recombination coefficient of H on a clean W surface is extremely high which indicates the rapid desorption of the hydrogen molecule from the surface. Simulation using a high recombination coefficient well describes a wide range of experimental data of gas and ions interaction of hydrogen isotopes with tungsten. Proof of incorrectness of the Anderl's recombination coefficient is presented by comparing it with both theory and experiment.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311515300702}, + doi = {10.1016/j.jnucmat.2015.06.048}, + abstract = {Hydrogen isotope behavior and inventory in plasma-facing components (PFCs) of fusion devices are key concerns for safe, reliable, and economical operation. To accurately estimate hydrogen isotope retention and recovery in tungsten (the current leading candidate as a PFC), we have developed a model that was recently benchmarked against isotope depth profile and retention level in a tungsten target under various conditions and compared with both experimental data and simulation results. In this research, we have extended the model to include details of transient events. Therefore, one can use this model to estimate hydrogen isotope retention behavior in tungsten and potential other PFC candidates during normal operational pulse, effects of edge-localized modes (ELMs), and a possible cleaning processes scenario.}, language = {en}, - urldate = {2020-04-01}, + urldate = {2020-06-19}, journal = {Journal of Nuclear Materials}, - author = {Ogorodnikova, O. V.}, + author = {Hu, Alice and Hassanein, Ahmed}, + month = oct, + year = {2015}, + keywords = {ITER, ELMs, Fusion devices, Plasma-facing components, Tritium retention}, + pages = {582--589}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\Y44Q5NHY\\S0022311515300702.html:text/html}, +} + +@article{bjorkas_variables_2013, + title = {Variables affecting simulated {Be} sputtering yields}, + volume = {439}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311513006363}, + doi = {10.1016/j.jnucmat.2013.04.036}, + abstract = {Since beryllium is a strong candidate for the main plasma-facing material in future fusion reactors, its sputtering behaviour plays an important role in predicting the reactor’s life-time. Consensus about the actual sputtering yields has not yet been achieved, as observations are influenced by experimental method and/or studied sample. In this work, the beryllium sputtering due to deuterium and beryllium self-bombardment is analyzed using molecular dynamics simulations. The main methodological aspects that influence the outcome, such as flux and fluence of the bombardment, are highlighted, and it is shown that the simulated yields also depend on the sample structure and deuterium content.}, + language = {en}, + number = {1}, + urldate = {2020-06-19}, + journal = {Journal of Nuclear Materials}, + author = {Björkas, C. and Nordlund, K.}, month = aug, - year = {2019}, - pages = {74--79}, - file = {Ogorodnikova - 2019 - Recombination coefficient of hydrogen on tungsten .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X5VH4RC2\\Ogorodnikova - 2019 - Recombination coefficient of hydrogen on tungsten .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RNBPEF6F\\S0022311519300030.html:text/html}, + year = {2013}, + pages = {174--179}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BKEBN2R2\\S0022311513006363.html:text/html}, } -@article{turnbull_modelling_1997, - title = {Modelling of thermal desorption of hydrogen from metals}, - volume = {238}, - issn = {0921-5093}, - url = {http://www.sciencedirect.com/science/article/pii/S0921509397004267}, - doi = {10.1016/S0921-5093(97)00426-7}, - abstract = {The thermal desorption technique can be used in principle to determine the trapping characteristics of different microstructural trap sites in metals provided there are adequate models to fit to the experimental data. A brief review of models of thermal desorption is presented which indicates that there are limitations in the assumptions made or in the scope of existing models. A more rigorous mathematical model has now been developed which accounts for diffusion, detrapping, and retrapping at one or more type of trap site and which allows for varying trap occupancy. The effect of material and experimental variables on the thermal desorption spectrum has been evaluated and the validity of simple models of desorption assessed. The simpler analytical models, such as the detrapping model of Lee and Lee, in which diffusion is neglected relative to detrapping, do not inspire confidence and are applicable only under very limiting circumstances; for example, in low alloy steels at very low hydrogen contents. It is recommended that thermal desorption measurements be made at progressively decreasing values of initial hydrogen content until the simple analysis yields a consistent value for the trapping parameters. This experimental approach is applicable also to models of thermal desorption which account for diffusion using an effective diffusivity, since trap occupancy is neglected in these. The more rigorous model described herein can be used to determine the binding energy of the traps directly which, together with the density of trap sites, is the most important parameter with respect to hydrogen assisted cracking. The height of the energy barrier to trapping, at constant value of the binding energy, is shown to have only a modest effect on the thermal desorption spectrum compared with the impact of binding energy and of density of trap sites.}, +@article{bisson_dynamic_2015, + title = {Dynamic fuel retention in tokamak wall materials: {An} in situ laboratory study of deuterium release from polycrystalline tungsten at room temperature}, + volume = {467}, + issn = {0022-3115}, + shorttitle = {Dynamic fuel retention in tokamak wall materials}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311515301148}, + doi = {10.1016/j.jnucmat.2015.07.028}, + abstract = {Retention of deuterium ion implanted in polycrystalline tungsten samples is studied in situ in an ultra-high vacuum apparatus equipped with a low-flux ion source and a high sensitivity thermo-desorption setup. Retention as a function of ion fluence was measured in the 1017–1021 D+·m−2 range. By combining this new fluence range with the literature in situ experimental data, we evidence the existence of a retention ∝ fluence0.645±0.025 relationship which describes deuterium retention behavior on polycrystalline tungsten on 8 orders of magnitude of fluence. Evolution of deuterium retention as a function of the sample storage time in vacuum at room temperature was followed. A loss of 50\% of the retained deuterium is observed when the storage time is increased from 2 h to 135 h. The role of the surface and of natural bulk defects on the deuterium retention/release in polycrystalline tungsten is discussed in light of the behavior of the single desorption peak obtained with Temperature Programmed Desorption.}, language = {en}, - number = {2}, - urldate = {2020-01-27}, - journal = {Materials Science and Engineering: A}, - author = {Turnbull, A and Hutchings, R. B and Ferriss, D. H}, - month = nov, - year = {1997}, - keywords = {Hydrogen, Metals, Modeling, Thermal desorption}, - pages = {317--328}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LL4BE5YA\\Turnbull et al. - 1997 - Modelling of thermal desorption of hydrogen from m.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7FVXEMJK\\S0921509397004267.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6KKKICHN\\Turnbull et al. - 1997 - Modelling of thermal desorption of hydrogen from m.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EC588WWB\\S0921509397004267.html:text/html}, + urldate = {2020-06-18}, + journal = {Journal of Nuclear Materials}, + author = {Bisson, R. and Markelj, S. and Mourey, O. and Ghiorghiu, F. and Achkasov, K. and Layet, J. -M. and Roubin, P. and Cartry, G. and Grisolia, C. and Angot, T.}, + month = dec, + year = {2015}, + keywords = {Tungsten, Deuterium, Fuel retention, Ion implantation, Plasma surface interaction, Thermodesorption, Tokamak}, + pages = {432--438}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EBXLLLF4\\S0022311515301148.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\I7QQX76X\\Bisson et al. - 2015 - Dynamic fuel retention in tokamak wall materials .pdf:application/pdf}, } -@article{denis_dynamic_2019, - title = {Dynamic modelling of local fuel inventory and desorption in the whole tokamak vacuum vessel for auto-consistent plasma-wall interaction simulations}, - volume = {19}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S235217911830262X}, - doi = {10.1016/j.nme.2019.03.019}, - abstract = {An extension of the SolEdge2D-EIRENE code package, named D-WEE, has been developed to add the dynamics of thermal desorption of hydrogen isotopes from the surface of plasma facing materials. To achieve this purpose, D-WEE models hydrogen isotopes implantation, transport and retention in those materials. Before launching auto-consistent simulation (with feedback of D-WEE on SolEdge2D-EIRENE), D-WEE has to be initialised to ensure a realistic wall behaviour in terms of dynamics (pumping or fuelling areas) and fuel content. A methodology based on modelling is introduced to perform such initialisation. A synthetic plasma pulse is built from consecutive SolEdge2D-EIRENE simulations. This synthetic pulse is used as a plasma background for the D-WEE module. A sequence of plasma pulses is simulated with D-WEE to model a tokamak operation. This simulation enables to extract at a desired time during a pulse the local fuel inventory and the local desorption flux density which could be used as initial condition for coupled plasma-wall simulations. To assess the relevance of the dynamic retention behaviour obtained in the simulation, a confrontation to post-pulse experimental pressure measurement is performed. Such confrontation reveals a qualitative agreement between the temporal pressure drop obtained in the simulation and the one observed experimentally. The simulated dynamic retention during the consecutive pulses is also studied.}, +@book{rasmussen_gaussian_2006, + title = {Gaussian {Processes} for {Machine} {Learning}}, + author = {Rasmussen, C. E and Williams, C. K. I.}, + year = {2006}, + file = {Rasmussen et Williams - 2006 - Gaussian Processes for Machine Learning.pdf:D\:\\Logiciels\\data_zotero\\storage\\32AWGKG7\\Rasmussen et Williams - 2006 - Gaussian Processes for Machine Learning.pdf:application/pdf}, +} + +@article{grisolia_plasma_1999, + title = {Plasma wall interaction during long pulse operation in {Tore} {Supra}}, + volume = {266-269}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311598008150}, + doi = {10.1016/S0022-3115(98)00815-0}, + abstract = {Increase of plasma density observed during long pulse operation is reported. The higher the injected and radiated energies are, the faster the increase of density appears. This behaviour correlated with oxygen and hydrogen plasma density increase is attributed to water desorption induced by wall heating due to the high radiated energy of the plasma. These surfaces are far from plasma and are not baked during the conditioning procedures usually used at Tore Supra. Conditioning evidence is seen during discharge series at high injected energy. But this improvement is prevented if disruptions occur in between.}, language = {en}, - urldate = {2020-03-13}, - journal = {Nuclear Materials and Energy}, - author = {Denis, J. and Bucalossi, J. and Ciraolo, G. and Hodille, E. A. and Pégourié, B. and Bufferand, H. and Grisolia, C. and Loarer, T. and Marandet, Y. and Serre, E.}, - month = may, - year = {2019}, - keywords = {Dynamic retention, Dynamics of hydrogen isotopes thermal desorption, Edge plasma physics, Plasma-wall interaction simulation, Recycling}, - pages = {550--557}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YKZINC8E\\Denis et al. - 2019 - Dynamic modelling of local fuel inventory and deso.pdf:application/pdf}, + urldate = {2020-06-16}, + journal = {Journal of Nuclear Materials}, + author = {Grisolia, C.}, + month = mar, + year = {1999}, + keywords = {Hydrogen, Carbon, Chemical erosion, Graphite, Ion Bombardment, Oxygen}, + pages = {146--152}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\LTDWZ3HT\\S0022311598008150.html:text/html}, } -@misc{noauthor_solute_nodate, - title = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment - {IOPscience}}, - url = {https://iopscience.iop.org/article/10.1088/1402-4896/ab4b42}, - urldate = {2020-03-30}, - file = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment - IOPscience:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TZ22YHLS\\ab4b42.html:text/html}, +@article{raissi_physics_2017, + title = {Physics {Informed} {Deep} {Learning} ({Part} {I}): {Data}-driven {Solutions} of {Nonlinear} {Partial} {Differential} {Equations}}, + shorttitle = {Physics {Informed} {Deep} {Learning} ({Part} {I})}, + url = {http://arxiv.org/abs/1711.10561}, + abstract = {We introduce physics informed neural networks -- neural networks that are trained to solve supervised learning tasks while respecting any given law of physics described by general nonlinear partial differential equations. In this two part treatise, we present our developments in the context of solving two main classes of problems: data-driven solution and data-driven discovery of partial differential equations. Depending on the nature and arrangement of the available data, we devise two distinct classes of algorithms, namely continuous time and discrete time models. The resulting neural networks form a new class of data-efficient universal function approximators that naturally encode any underlying physical laws as prior information. In this first part, we demonstrate how these networks can be used to infer solutions to partial differential equations, and obtain physics-informed surrogate models that are fully differentiable with respect to all input coordinates and free parameters.}, + urldate = {2020-06-15}, + journal = {arXiv:1711.10561 [cs, math, stat]}, + author = {Raissi, Maziar and Perdikaris, Paris and Karniadakis, George Em}, + month = nov, + year = {2017}, + note = {arXiv: 1711.10561}, + keywords = {Computer Science - Artificial Intelligence, Computer Science - Machine Learning, Mathematics - Dynamical Systems, Mathematics - Numerical Analysis, Statistics - Machine Learning}, + file = {arXiv Fulltext PDF:D\:\\Logiciels\\data_zotero\\storage\\QR2ZZBH2\\Raissi et al. - 2017 - Physics Informed Deep Learning (Part I) Data-driv.pdf:application/pdf;arXiv.org Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QLM9WJZD\\1711.html:text/html}, } -@misc{noauthor_shape_nodate, - title = {The shape of bubbles in {He}-implanted {Cu} and {Au} - {ScienceDirect}}, - url = {https://www.sciencedirect.com/science/article/pii/S135964621000299X}, - urldate = {2020-03-16}, - keywords = {Bubbles}, - file = {The shape of bubbles in He-implanted Cu and Au - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YKBGS6KT\\S135964621000299X.html:text/html}, +@misc{chris_bowman_c-bowmaninference-tools_2020, + title = {C-bowman/inference-tools: 0.5.3 release}, + shorttitle = {C-bowman/inference-tools}, + url = {https://zenodo.org/record/3757497#.XueCdUUzaUm}, + abstract = {Rather than assuming the mean of the Gaussian process is zero, GpRegressor now treats the mean as a hyper-parameter, and automatically selects a value for the mean which best describes the data. Fixed a bug in the calculation of the derivatives of the log-marginal-likelihood and the log-cross-validation density with respect to the hyper-parameters.}, + urldate = {2020-06-15}, + publisher = {Zenodo}, + author = {Chris Bowman}, + month = apr, + year = {2020}, + doi = {10.5281/zenodo.3757497}, + file = {Zenodo Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NV9AGYC4\\3757497.html:text/html}, } -@article{benannoune_multidimensional_2020, - title = {Multidimensional finite-element simulations of the diffusion and trapping of hydrogen in plasma-facing components including thermal expansion}, - volume = {T171}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F1402-4896%2Fab4335}, - doi = {10.1088/1402-4896/ab4335}, - abstract = {This study is focused on tritium retention and permeation through a 316L stainless steel diagnostic first wall during plasma operations in ITER. A set of data for migration properties is proposed by adjusting the values to fit a simulation using experimental results. A reactive–diffusion model coupled with a mechanical field, solved on 3DS Abaqus finite-element software, is applied to estimate tritium migration. Two-dimensional simulations are compared with one-dimensional simulations and the role of thermal expansion on plastic deformation and trap creation is discussed.}, +@article{hirai_design_2018, + title = {Design optimization of the {ITER} tungsten divertor vertical targets}, + volume = {127}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379617309596}, + doi = {10.1016/j.fusengdes.2017.12.007}, + abstract = {The shaping of the ITER divertor vertical targets has been refined as a consequence of manufacturing and engineering considerations during the prototype manufacturing activities. In this paper, the optimized ITER divertor design is presented together with design validation by 3D field line tracing calculation and thermo-mechanical analysis by finite element calculations. Furthermore, the reduction of W monoblock armour thickness to 6 mm is also discussed.}, language = {en}, - urldate = {2020-03-13}, - journal = {Physica Scripta}, - author = {Benannoune, Sofiane and Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique and Temmerman, Greg De}, - month = jan, - year = {2020}, - pages = {014011}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\95HNAEV2\\Benannoune et al. - 2020 - Multidimensional finite-element simulations of the.pdf:application/pdf}, + urldate = {2020-06-03}, + journal = {Fusion Engineering and Design}, + author = {Hirai, T. and Carpentier-Chouchana, S. and Escourbiac, F. and Panayotis, S. and Durocher, A. and Ferrand, L. and Garcia-Martinez, M. and Gunn, J. P. and Komarov, V. and Merola, M. and Pitts, R. A. and De Temmerman, G.}, + month = feb, + year = {2018}, + keywords = {Tungsten, ITER, High heat flux, Divertor, Leading edge, Monoblock}, + pages = {66--72}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5N56PMAR\\Hirai et al. - 2018 - Design optimization of the ITER tungsten divertor .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\HF8X8DKF\\S0920379617309596.html:text/html}, +} + +@article{bonnin_presentation_2016, + title = {Presentation of the {New} {SOLPS}-{ITER} {Code} {Package} for {Tokamak} {Plasma} {Edge} {Modelling}}, + volume = {11}, + doi = {10.1585/pfr.11.1403102}, + abstract = {We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas in the edge region of fusion devices. This package brings together previously existing SOLPS implementations and aims to become the new standard SOLPS version. We summarize the benchmarking work done to ensure backward compatibility with previous work, with a strong requirement on maintaining the viability and usability of the already extensive database of SOLPS runs used for the ITER divertor design and edge plasma physics studies worldwide over the years. The SOLPS-ITER package includes not only the plasma (B2.5) and neutral (Eirene) transport solvers, but also a large set of software tools for input file build-up, conversion of old runs, inline run analysis, and post-processing, all within a standardized portable run environment and version control system. Ongoing and planned upgrades to the code, such as extending the computational domain to the full vacuum vessel wall and a new graphical user interface, are also discussed.}, + journal = {Plasma and Fusion Research}, + author = {Bonnin, Xavier and Dekeyser, Wouter and Pitts, Richard and Coster, David and Voskoboynikov, Serguey and Wiesen, Sven}, + year = {2016}, + keywords = {B2.5-Eirene, plasma code, plasma edge, plasma modelling, SOLPS-ITER}, + pages = {1403102--1403102}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SK4DMVMV\\Bonnin et al. - 2016 - Presentation of the New SOLPS-ITER Code Package fo.pdf:application/pdf;J-Stage - Snapshot:D\:\\Logiciels\\data_zotero\\storage\\WDBIAHM9\\_article.html:text/html}, } -@article{khan_helium_2020, - title = {Helium irradiation effects on the surface modification and recrystallization of tungsten}, - volume = {T171}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F1402-4896%2Fab52c6}, - doi = {10.1088/1402-4896/ab52c6}, - abstract = {Helium (He) irradiation has previously been observed to alter surface modifications and the recrystallization properties of tungsten (W). In this study, He irradiations in the NAGDIS-II linear plasma device, at temperatures below recrystallization and low energies (50 eV) followed by annealing at 1470 K were carried out. Additionally, high energy (28 keV) hydrogen (H) with an admixture of 6 at\% He irradiations in the neutral beam facility GLADIS were performed at temperatures above recrystallization (1770 K). These are compared to pure H irradiations under the same conditions. In the low temperature cases, following irradiation, an undulating microstructure is observed on the surface of the samples after irradiation. After annealing at 1470 K, it is observed that the inhibition effect of He irradiation is more pronounced following lower temperature exposures. The effect of He irradiation on inhibition of recrystallization with grain growth is also observed to saturate at the highest fluences. In the high temperature, high energy case, He irradiation and recrystallization happens simultaneously. Following the irradiation a coral like microstructure is observed on the surface of the sample. The introduction of He is not seen to have a significant effect on the recrystallization process of W when the irradiation is carried out at temperatures above recrystallization.}, +@article{gu_quantifying_2018, + title = {Quantifying the effect of hydrogen on dislocation dynamics: {A} three-dimensional discrete dislocation dynamics framework}, + volume = {112}, + issn = {0022-5096}, + shorttitle = {Quantifying the effect of hydrogen on dislocation dynamics}, + url = {http://www.sciencedirect.com/science/article/pii/S0022509617309079}, + doi = {10.1016/j.jmps.2018.01.006}, + abstract = {We present a new framework to quantify the effect of hydrogen on dislocations using large scale three-dimensional (3D) discrete dislocation dynamics (DDD) simulations. In this model, the first order elastic interaction energy associated with the hydrogen-induced volume change is accounted for. The three-dimensional stress tensor induced by hydrogen concentration, which is in equilibrium with respect to the dislocation stress field, is derived using the Eshelby inclusion model, while the hydrogen bulk diffusion is treated as a continuum process. This newly developed framework is utilized to quantify the effect of different hydrogen concentrations on the dynamics of a glide dislocation in the absence of an applied stress field as well as on the spacing between dislocations in an array of parallel edge dislocations. A shielding effect is observed for materials having a large hydrogen diffusion coefficient, with the shield effect leading to the homogenization of the shrinkage process leading to the glide loop maintaining its circular shape, as well as resulting in a decrease in dislocation separation distances in the array of parallel edge dislocations. On the other hand, for materials having a small hydrogen diffusion coefficient, the high hydrogen concentrations around the edge characters of the dislocations act to pin them. Higher stresses are required to be able to unpin the dislocations from the hydrogen clouds surrounding them. Finally, this new framework can open the door for further large scale studies on the effect of hydrogen on the different aspects of dislocation-mediated plasticity in metals. With minor modifications of the current formulations, the framework can also be extended to account for general inclusion-induced stress field in discrete dislocation dynamics simulations.}, language = {en}, - urldate = {2020-03-13}, - journal = {Physica Scripta}, - author = {Khan, A. and Temmerman, G. De and Kajita, S. and Greuner, H. and Balden, M. and Hunger, K. and Ohno, N. and Hwangbo, D. and Tomita, Y. and Tokitani, M. and Nagata, D. and Yajima, M.}, - month = jan, - year = {2020}, - pages = {014050}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\J2Z897XD\\Khan et al. - 2020 - Helium irradiation effects on the surface modifica.pdf:application/pdf}, + urldate = {2020-05-28}, + journal = {Journal of the Mechanics and Physics of Solids}, + author = {Gu, Yejun and El-Awady, Jaafar A.}, + month = mar, + year = {2018}, + keywords = {Hydrogen, Diffusion, Discrete dislocation dynamics, Embrittlement}, + pages = {491--507}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CEFLD9Z6\\S0022509617309079.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\CLZFRTAL\\Gu et El-Awady - 2018 - Quantifying the effect of hydrogen on dislocation .pdf:application/pdf}, } -@article{sharafat_description_2009, - series = {Fusion {Reactor} {Materials}}, - title = {A description of bubble growth and gas release of helium implanted tungsten}, - volume = {386-388}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311508010155}, - doi = {10.1016/j.jnucmat.2008.12.318}, - abstract = {Bubble growth and gas release during annealing of helium implanted tungsten is described using a Kinetic Monte Carlo approach. Implantation of tungsten with low energy He ions results in the unusual formation of large numbers of oversized surface pores, which eventually lead to drastic changes of the tungsten surface morphology. Traditional rate-theory models are not suitable to simulate surface pore formation. Results of the KMC simulations illustrate the rapid formation of very large helium bubbles and surface pores. The simulation results agree well with observed results of low energy He implanted tungsten experiments, and thus provide an explanation for the observed surface morphology changes caused by low energy He implantation of tungsten.}, +@article{jang_advanced_2008, + title = {Advanced {Thermal}-{Moisture} {Analogy} {Scheme} for {Anisothermal} {Moisture} {Diffusion} {Problem}}, + volume = {130}, + issn = {1043-7398}, + url = {https://asmedigitalcollection.asme.org/electronicpackaging/article/130/1/011004/455172/Advanced-Thermal-Moisture-Analogy-Scheme-for}, + doi = {10.1115/1.2837521}, language = {en}, - urldate = {2020-03-11}, - journal = {Journal of Nuclear Materials}, - author = {Sharafat, S. and Takahashi, A. and Hu, Q. and Ghoniem, N. M.}, - month = apr, - year = {2009}, - pages = {900--903}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UWY9JXNY\\Sharafat et al. - 2009 - A description of bubble growth and gas release of .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\E8DC44B6\\S0022311508010155.html:text/html}, + number = {1}, + urldate = {2020-05-28}, + journal = {Journal of Electronic Packaging}, + author = {Jang, Changsoo and Park, Seungbae and Han, Bongtae and Yoon, Samson}, + month = mar, + year = {2008}, + note = {Publisher: American Society of Mechanical Engineers Digital Collection}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9HTI7RFK\\Advanced-Thermal-Moisture-Analogy-Scheme-for.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\9X6T547N\\Jang et al. - 2008 - Advanced Thermal-Moisture Analogy Scheme for Aniso.pdf:application/pdf}, } -@article{reinhart_diffusion_2019, - title = {Diffusion model of the impact of helium and argon impurities on deuterium retention in tungsten}, - volume = {59}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Faafe8d}, - doi = {10.1088/1741-4326/aafe8d}, - abstract = {The influence of helium and argon impurities on the deuterium retention in tungsten is investigated by a numerical diffusion model, which treats diffusing depth profiles for deuterium and helium or argon in tungsten, taking into account the suggested effects of helium or argon. With helium, a helium nanobubble layer builds up at the surface of the sample, with depths higher than the penetration depth of the incident helium and deuterium ions. The nanobubbles form a porous network, which allows the release of trapped deuterium by surface recombination and diffusion through the pores to the surface. For argon, only a shallow layer of argon-induced defects exists, which also act as trapping sites for deuterium. A number of experiments with tungsten samples were conducted at the linear plasma device PSI-2 in support of the model. Helium and argon were admixed to deuterium plasma in ratios of up to 8\% for otherwise similar exposure conditions. In addition, a variation of ion fluences was performed for investigation of the onset and evolution of the effects of impurities. The model shows that the influence on the deuterium retention both for helium nanobubbles as well as for argon-induced defects depends strongly on the ratio between the thickness of the helium- or argon-affected layer and the penetration depth of deuterium ions.}, +@article{yoon_moisture_2007, + title = {On {Moisture} {Diffusion} {Modeling} {Using} {Thermal}-{Moisture} {Analogy}}, + volume = {129}, + issn = {1043-7398}, + url = {https://asmedigitalcollection.asme.org/electronicpackaging/article/129/4/421/470212/On-Moisture-Diffusion-Modeling-Using-Thermal}, + doi = {10.1115/1.2804090}, language = {en}, number = {4}, - urldate = {2020-03-11}, - journal = {Nuclear Fusion}, - author = {Reinhart, M. and Kreter, A. and Unterberg, B. and Rasinski, M. and Linsmeier, Ch}, - month = feb, - year = {2019}, - pages = {046004}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I7IFR6XF\\Reinhart et al. - 2019 - Diffusion model of the impact of helium and argon .pdf:application/pdf}, -} - -@misc{noauthor_theoretical_nodate, - title = {Theoretical {Model} of {Helium} {Bubble} {Growth} and {Density} in {Plasma}-{Facing} {Metals} {\textbar} {Scientific} {Reports}}, - url = {https://www.nature.com/articles/s41598-020-58581-8}, - urldate = {2020-03-10}, - file = {Theoretical Model of Helium Bubble Growth and Density in Plasma-Facing Metals | Scientific Reports:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5EPBJHSA\\s41598-020-58581-8.html:text/html}, + urldate = {2020-05-28}, + journal = {Journal of Electronic Packaging}, + author = {Yoon, Samson and Han, Bongtae and Wang, Zhaoyang}, + month = dec, + year = {2007}, + note = {Publisher: American Society of Mechanical Engineers Digital Collection}, + pages = {421--426}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SCD6GFTU\\On-Moisture-Diffusion-Modeling-Using-Thermal.html:text/html}, } -@article{mikhlin_suppression_1979, - title = {Suppression of diffusion mobility of small gas bubbles in solids}, - volume = {56}, - issn = {00318965, 1521396X}, - url = {http://doi.wiley.com/10.1002/pssa.2210560244}, - doi = {10.1002/pssa.2210560244}, +@article{xu_transport_2020, + title = {Transport parameters and permeation behavior of hydrogen isotopes in the first wall materials of future fusion reactors}, + volume = {155}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620301113}, + doi = {10.1016/j.fusengdes.2020.111563}, + abstract = {The first wall of a future magnetic fusion device is essentially defined as the plasma-facing surface of the breeding blankets, which is supposed to be subjected to bi-directional hydrogen isotopes permeation: in one direction by edge plasma-driven permeation (PDP) of deuterium as well as tritium into blankets, and in the other direction by breed tritium gas-driven permeation (GDP) into the edge plasma. Deuterium and tritium PDP will complicate the recovery of tritium from the blanket, while tritium GDP will lead to an unwanted increase of particle recycling in the first wall region, which could even affect core confinement performance. Reduced activation ferritic/martensitic (RAFM) steels are widely proposed as candidate structural materials for the blanket of a DEMO reactor, the surface coatings made of tungsten are necessary to protect the plasma-facing wall from sputtering under high-energy particle bombardment. Therefore, the characterization of hydrogen isotopes transport through a multi-layer W + RAFM wall is of crucial importance to evaluate major reactor design issues including tritium retention, particle recycling and breeding feasibility, etc. This paper is intended to provide a review over the transport parameters of hydrogen isotopes in RAFM steels, including permeability, diffusivity, solubility and surface recombination coefficient. In addition, the present research status of hydrogen isotopes permeation and retention behavior of tungsten coated RAFM steels is briefly introduced.}, language = {en}, - number = {2}, - urldate = {2020-03-10}, - journal = {Physica Status Solidi (a)}, - author = {Mikhlin, E. Ya.}, - month = dec, - year = {1979}, - pages = {763--768}, - file = {Mikhlin - 1979 - Suppression of diffusion mobility of small gas bub.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S33BVJSI\\Mikhlin - 1979 - Suppression of diffusion mobility of small gas bub.pdf:application/pdf}, + urldate = {2020-05-26}, + journal = {Fusion Engineering and Design}, + author = {Xu, Yue and Wu, Zuo-Sheng and Luo, Lai-Ma and Zan, Xiang and Zhu, Xiao-Yong and Xu, Qiu and Wu, Yu-Cheng}, + month = jun, + year = {2020}, + keywords = {First wall, Deuterium retention, Hydrogen isotopes permeation, Transport parameters, Tungsten coatings}, + pages = {111563}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SBXMAP84\\Xu et al. - 2020 - Transport parameters and permeation behavior of hy.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4IMQ4RLP\\S0920379620301113.html:text/html}, } -@article{connetable_diffusion_2019, - title = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd}): {Contribution} of first and second order transition states}, - volume = {772}, - issn = {0925-8388}, - shorttitle = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd})}, - url = {http://www.sciencedirect.com/science/article/pii/S0925838818332717}, - doi = {10.1016/j.jallcom.2018.09.042}, - abstract = {We present a discussion on the influence of high-order transition states on interstitial diffusion in fcc systems using first-principles calculations. In earlier works, only first-order transition states (1TS) were used to compute the diffusivity at the atomic-scale: the direct diffusion between tetrahedral (t) and octahedral (o) sites has been proposed to describe atomic-scale diffusion mechanisms. However, we show here that if this direct diffusion makes it possible to reproduce displacements remarkably well, neglecting higher-order transition states induces an underestimation of the diffusion coefficient at high temperature. We hereinafter revisit the diffusion coefficient of interstitial species in different fcc-systems. The effect of these configurations on atom diffusion in Al, Co, Cu, Ni and Pd, whose only stable sites are the tetrahedral and octahedral positions (H and O atoms) is thus discussed here. We show that if the correction is low, taking into account higher-transition states can modify the diffusivity values at high temperature.}, +@article{richou_realization_2017, + title = {Realization of high heat flux tungsten monoblock type target with graded interlayer for application to {DEMO} divertor}, + volume = {T170}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F1402-4896%2Faa8b02}, + doi = {10.1088/1402-4896/aa8b02}, + abstract = {The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. In DEMO, divertor targets must survive an environment of high heat fluxes (∼up to 20 MW m−2 during slow transients) and neutron irradiation. One advanced concept for components in monoblock configuration concerns the insertion of a compositionally graded layer between tungsten and CuCrZr instead of the soft copper interlayer. As a first step, a thin graded layer (∼25 μm) was developed. As a second step, a thicker graded layer (∼500 μm), which is actually being developed, will also be inserted to study the compliant role of a macroscopic graded layer. This paper reports the results of cyclic high heat flux loading tests up to 20 MW m−2 and to heat flux higher than 25 MW m−2 that mock-ups equipped with thin graded layer survived without visible damage. First feedback on manufacturing steps is also presented. Moreover, the first results obtained on the development of the thick graded layer and its integration in a monoblock configuration are shown.}, language = {en}, - urldate = {2020-02-14}, - journal = {Journal of Alloys and Compounds}, - author = {Connétable, Damien and David, Matthieu}, - month = jan, - year = {2019}, - keywords = {Diffusion, DFT, DFT calculations, Hydrogen and oxygen, Metallic systems}, - pages = {280--287}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8KREWJZK\\Connétable et David - 2019 - Diffusion of interstitial species (H and O atoms) .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TIS3CMIZ\\S0925838818332717.html:text/html}, + urldate = {2020-05-25}, + journal = {Physica Scripta}, + author = {Richou, M. and Gallay, F. and Böswirth, B. and Chu, I. and Lenci, M. and Loewenhoff, Th and Quet, A. and Greuner, H. and Kermouche, G. and Meillot, E. and Pintsuk, G. and Visca, E. and You, J. H.}, + month = oct, + year = {2017}, + note = {Publisher: IOP Publishing}, + pages = {014022}, } -@misc{noauthor_diffusion_nodate, - title = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd}): {Contribution} of first and second order transition states - {ScienceDirect}}, - url = {https://www.sciencedirect.com/science/article/pii/S0925838818332717?via%3Dihub}, - urldate = {2020-02-14}, - file = {Diffusion of interstitial species (H and O atoms) in fcc systems (Al, Cu, Co, Ni and Pd)\: Contribution of first and second order transition states - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2W724AJV\\S0925838818332717.html:text/html}, +@inproceedings{ahrens_paraview_2005, + title = {{ParaView}: {An} {End}-{User} {Tool} for {Large}-{Data} {Visualization}}, + shorttitle = {{ParaView}}, + doi = {10.1016/B978-012387582-2/50038-1}, + abstract = {This chapter describes the design and features of a visualization tool called ParaView, a tool that allows scientists to visualize and analyze extremely large datasets. The tool provides a graphical user interface for the creation and dynamic execution of visualization tasks. ParaView transparently supports the visualization and rendering of large datasets by executing these programs in parallel on shared or distributed memory machines. ParaView supports hardware-accelerated parallel rendering and achieves interactive rendering performance via level-of-detail techniques. The design balances and integrates a number of diverse requirements, including the ability to handle large data, ease of use, and extensibility by developers. The chapter describes the requirements that guided the design, identifies the importance of those requirements to scientific users, and discusses key design decisions and tradeoffs.}, + booktitle = {The {Visualization} {Handbook}}, + author = {Ahrens, James Paul and Geveci, Berk and Law, Charles Chi Wang}, + year = {2005}, } -@article{zibrov_experimental_2016, - title = {Experimental determination of the deuterium binding energy with vacancies in tungsten}, - volume = {477}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S002231151630174X}, - doi = {10.1016/j.jnucmat.2016.04.052}, - abstract = {Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectroscopy (TDS). In order to obtain a TDS spectrum with a prominent peak corresponding to D release from vacancies, a special procedure comprising damaging of a recrystallized W sample by low fluences of 10 keV/D ions, its annealing, and subsequent low-energy ion implantation, was utilized. This experimental sequence was performed several times in series; the only difference was the TDS heating rate that varied in the range of 0.15–4 K/s. The sum of the D binding energy (Eb) with vacancies and the activation energy for D diffusion (ED) in W was then directly determined from the slope of the Arrhenius-like plot ln(β/Tm2) versus 1/Tm, where β – heating rate and Tm – position of the respective peak in the TDS spectrum. The determined value of Eb + ED was 1.56 ± 0.06 eV.}, +@article{simmonds_tmap_2020, + title = {{TMAP} modeling of {D} release from baked multi-layer {Be}–{D} co-deposits}, + volume = {T171}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F1402-4896%2Fab4de4}, + doi = {10.1088/1402-4896/ab4de4}, + abstract = {Single-layer Beryllium–Deuterium (Be–D) co-deposits were analyzed using Thermal Desorption mass Spectrometry (TDS) as outlined in the companion paper (Baldwin et al 2019 Phys. Scr. PFMC Proc.). This work details the TMAP modeling and the analysis of selected samples that received double-layer (DL) coatings to study co-deposit thickness and prior bake effects. TDS data were simulated with detrap energies 0.8, 0.9, and 1.0 eV. In DLs formed at 393 K, modeling revealed that under-layers baked at 623 K for either 2 or 20 h had little pumping effect on over-layers, suggesting empty trap removal during bake. Extrapolated to ITER, data and analysis suggest less impact on the ongoing ITER bake efficiency than previously predicted (Baldwin and Doerner 2015 J. Nucl. Mater. 467 38391).}, language = {en}, - urldate = {2020-02-13}, - journal = {Journal of Nuclear Materials}, - author = {Zibrov, M. and Ryabtsev, S. and Gasparyan, Yu. and Pisarev, A.}, - month = aug, - year = {2016}, - keywords = {Tungsten, Deuterium, Vacancies, Thermal desorption, Binding energy, Radiation defects, TDS}, - pages = {292--297}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WFCSGD3V\\Zibrov et al. - 2016 - Experimental determination of the deuterium bindin.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HFE89QV4\\S002231151630174X.html:text/html}, + urldate = {2020-05-11}, + journal = {Physica Scripta}, + author = {Simmonds, M. J. and Baldwin, M. J. and Temmerman, G. De and Doerner, R. P.}, + month = jan, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {014043}, } -@article{rougier_ten_2014, - title = {Ten {Simple} {Rules} for {Better} {Figures}}, - volume = {10}, - issn = {1553-7358}, - url = {https://journals.plos.org/ploscompbiol/article?id=10.1371/journal.pcbi.1003833}, - doi = {10.1371/journal.pcbi.1003833}, - language = {en}, - number = {9}, - urldate = {2020-02-07}, - journal = {PLOS Computational Biology}, - author = {Rougier, Nicolas P. and Droettboom, Michael and Bourne, Philip E.}, - month = sep, - year = {2014}, - keywords = {Data visualization, Eye movements, Radii, Research design, Seismic signal processing, Software design, Software tools, Vision}, - pages = {e1003833}, - file = {Rougier et al. - 2014 - Ten Simple Rules for Better Figures.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TC2ZSRL3\\Rougier et al. - 2014 - Ten Simple Rules for Better Figures.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FVRXHZR8\\article.html:text/html}, +@article{hunter_matplotlib_2007, + title = {Matplotlib: {A} {2D} {Graphics} {Environment}}, + volume = {9}, + issn = {1558-366X}, + shorttitle = {Matplotlib}, + doi = {10.1109/MCSE.2007.55}, + abstract = {Matplotlib is a 2D graphics package used for Python for application development, interactive scripting,and publication-quality image generation across user interfaces and operating systems}, + number = {3}, + journal = {Computing in Science Engineering}, + author = {Hunter, John D.}, + month = may, + year = {2007}, + note = {Conference Name: Computing in Science Engineering}, + keywords = {2D graphics package, application development, computer graphics, Computer languages, Equations, Graphical user interfaces, Graphics, Image generation, interactive scripting, Interpolation, mathematics computing, Matplotlib, object-oriented programming, operating system, Operating systems, Packaging, Programming profession, publication-quality image generation, Python, scientific programming, scripting languages, software packages, user interface, User interfaces}, + pages = {90--95}, + file = {IEEE Xplore Abstract Record:D\:\\Logiciels\\data_zotero\\storage\\U7UCDQY3\\4160265.html:text/html}, } -@article{claeys_critical_2020, - title = {Critical assessment of the evaluation of thermal desorption spectroscopy data for duplex stainless steels: {A} combined experimental and numerical approach}, - volume = {186}, - issn = {1359-6454}, - shorttitle = {Critical assessment of the evaluation of thermal desorption spectroscopy data for duplex stainless steels}, - url = {http://www.sciencedirect.com/science/article/pii/S1359645420300112}, - doi = {10.1016/j.actamat.2019.12.055}, - abstract = {The present study evaluates thermal desorption spectroscopy (TDS) data measured for UNS S32205 duplex stainless steel. Variations in the TDS spectra are obtained by electrochemical hydrogen charging for different times and by applying different heating rates for desorption to evaluate the desorption activation energy. Good agreement is found when comparing the experimental TDS curves with the desorption flux based on a numerical diffusion model using a homogeneous average hydrogen diffusion coefficient for the two-phase (ferrite-austenite) duplex microstructure. Trapping cannot be distinguished from the experimental TDS data since hydrogen diffusion in austenite is the rate-determining process during desorption. An average diffusion activation energy of 43.4 kJ/mol is determined from the experiments. Moreover, similar findings are obtained with a finite-element model that includes the heterogeneous hydrogen-related properties of the two phases of this duplex stainless steel.}, +@article{schmid_recent_2017, + title = {Recent progress in the understanding of {H} transport and trapping in {W}}, + volume = {T170}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F1402-4896%2Faa8de0}, + doi = {10.1088/1402-4896/aa8de0}, + abstract = {The retention of hydrogen isotopes (HIs) (H, D and T) in the first, plasma exposed wall is one of the key concerns for the operation of future long pulse fusion devices. It affects the particle-, momentum- and energy balance in the scrape off layer as well as the retention of HIs and their permeation into the coolant. The currently accepted picture that is used for interpreting current laboratory and tokamak experiments is that of diffusion hindered by trapping at lattice defects. This paper summarises recent results that show that this current picture of how HIs are transported and retained in W needs to be extended: the modification of the surface (e.g. blistering) can lead to the formation of fast loss channels for near surface HIs. Trapping at single occupancy traps with fixed de-trapping energy fails to explain isotope exchange experiments, instead a trapping model with multi occupancy traps and fill level dependent de-trapping energies is required. The presence of interstitial impurities like N or C may affect the transport of solute HI. The presence of HIs during damage creation by e.g. neutrons stabilises defects and reduces defect annealing at elevated temperatures.}, language = {en}, - urldate = {2020-01-31}, - journal = {Acta Materialia}, - author = {Claeys, L. and Cnockaert, V. and Depover, T. and De Graeve, I. and Verbeken, K.}, - month = mar, - year = {2020}, - keywords = {Hydrogen diffusion, Diffusion activation energy, Duplex stainless steel, Hydrogen trapping, Thermal desorption spectroscopy}, - pages = {190--198}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EA9S9IRD\\Claeys et al. - 2020 - Critical assessment of the evaluation of thermal d.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NVYCIVZQ\\S1359645420300112.html:text/html}, + urldate = {2020-05-05}, + journal = {Physica Scripta}, + author = {Schmid, K. and Bauer, J. and Schwarz-Selinger, T. and Markelj, S. and Toussaint, U. v and Manhard, A. and Jacob, W.}, + month = oct, + year = {2017}, + note = {Publisher: IOP Publishing}, + pages = {014037}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\BLGHXCG4\\Schmid et al. - 2017 - Recent progress in the understanding of H transpor.pdf:application/pdf}, +} + +@book{noauthor_python_2010, + address = {London ; New York}, + title = {Python {Programming} {Fundamentals}}, + isbn = {978-1-84996-536-1}, + abstract = {Computer programming is a skill that can bring great enjoyment from the creativity involved in designing and implementing a solution to a problem. This classroom-tested and easy-to-follow textbook teaches the reader how to program using Python, an accessible language which can be learned incrementally. Through an extensive use of examples and practical exercises, students will learn to recognize and apply abstract patterns in programming, as well as how to inspect the state of a program using a debugger tool. Features: contains numerous examples and solved practice exercises designed for an interactive classroom environment; highlights several patterns which commonly appear in programs, and presents exercises that reinforce recognition and application of these patterns; introduces the use of a debugger, and includes supporting material that reveals how programs work; presents the Tkinter framework for building graphical user interface applications and event-driven programs; provides helpful additional resources for instructors at the associated website: http://cs.luther.edu/{\textasciitilde}leekent/CS1. This hands-on textbook for active learning in the classroom will enable undergraduates in computer science to develop the necessary skills to begin developing their own programs. It employs Python as the introductory language due to the wealth of support available for programmers.}, + language = {Anglais}, + publisher = {Springer London Ltd}, + month = oct, + year = {2010}, + file = {2010 - Python Programming Fundamentals.pdf:D\:\\Logiciels\\data_zotero\\storage\\BKB9KXUX\\2010 - Python Programming Fundamentals.pdf:application/pdf}, } -@article{hurley_numerical_2015, - title = {Numerical modeling of thermal desorption mass spectroscopy ({TDS}) for the study of hydrogen diffusion and trapping interactions in metals}, - volume = {40}, - issn = {0360-3199}, - url = {http://www.sciencedirect.com/science/article/pii/S0360319915000051}, - doi = {10.1016/j.ijhydene.2015.01.001}, - abstract = {Deriving the kinetic reaction constants associated with hydrogen diffusion and trapping in metals from thermal desorption mass spectroscopy (TDS) spectra proves to be complicated and the existing analysis methods are subject to debate. This article will provide a brief background of several commonly employed analysis techniques and discuss the necessity of a more complex and rigorous analysis method for the determination of the kinetic constants associated with hydrogen trapping interactions. Furthermore, a numerical simulation method will be proposed using the McNabb \& Foster equations to fit experimental TDS spectra in order to derive both diffusion and trapping/detrapping parameters, including the respective pre-exponential constants and activation energies associated with these interactions in metals.}, +@book{witelski_methods_2015, + series = {Springer {Undergraduate} {Mathematics} {Series}}, + title = {Methods of {Mathematical} {Modelling}: {Continuous} {Systems} and {Differential} {Equations}}, + isbn = {978-3-319-23041-2}, + shorttitle = {Methods of {Mathematical} {Modelling}}, + url = {https://www.springer.com/gp/book/9783319230412}, + abstract = {This book presents mathematical modelling and the integrated process of formulating sets of equations to describe real-world problems. It describes methods for obtaining solutions of challenging differential equations stemming from problems in areas such as chemical reactions, population dynamics, mechanical systems, and fluid mechanics.Chapters 1 to 4 cover essential topics in ordinary differential equations, transport equations and the calculus of variations that are important for formulating models. Chapters 5 to 11 then develop more advanced techniques including similarity solutions, matched asymptotic expansions, multiple scale analysis, long-wave models, and fast/slow dynamical systems.Methods of Mathematical Modelling will be useful for advanced undergraduate or beginning graduate students in applied mathematics, engineering and other applied sciences.}, language = {en}, - number = {8}, - urldate = {2020-01-28}, - journal = {International Journal of Hydrogen Energy}, - author = {Hurley, Caitlin and Martin, Frantz and Marchetti, Loïc and Chêne, Jacques and Blanc, Christine and Andrieu, Eric}, - month = mar, + urldate = {2020-05-04}, + publisher = {Springer International Publishing}, + author = {Witelski, Thomas and Bowen, Mark}, year = {2015}, - keywords = {Hydrogen, Diffusion, Hydrogen embrittlement, TDS, Numerical modeling, Thermal desorption mass spectroscopy, Trapping}, - pages = {3402--3414}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PBV2Z33N\\Hurley et al. - 2015 - Numerical modeling of thermal desorption mass spec.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VH6Z2CII\\S0360319915000051.html:text/html}, + doi = {10.1007/978-3-319-23042-9}, + file = {Witelski et Bowen - 2015 - Methods of Mathematical Modelling Continuous Syst.pdf:D\:\\Logiciels\\data_zotero\\storage\\BMVRPS9M\\Witelski et Bowen - 2015 - Methods of Mathematical Modelling Continuous Syst.pdf:application/pdf}, } -@article{backer_multiscale_2017, - title = {Multiscale modelling of the interaction of hydrogen with interstitial defects and dislocations in {BCC} tungsten}, - volume = {58}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Faa8e0c}, - doi = {10.1088/1741-4326/aa8e0c}, - abstract = {In a fusion tokamak, the plasma of hydrogen isotopes is in contact with tungsten at the surface of a divertor. In the bulk of the material, the hydrogen concentration profile tends towards dynamic equilibrium between the flux of incident ions and their trapping and release from defects, either native or produced by ion and neutron irradiation. The dynamics of hydrogen exchange between the plasma and the material is controlled by pressure, temperature, and also by the energy barriers characterizing hydrogen diffusion in the material, trapping and de-trapping from defects. In this work, we extend the treatment of interaction of hydrogen with vacancy-type defects, and investigate how hydrogen is trapped by self-interstitial atom defects and dislocations. The accumulation of hydrogen on dislocation loops and dislocations is assessed using a combination of density functional theory (DFT), molecular dynamics with empirical potentials, and linear elasticity theory. The equilibrium configurations adopted by hydrogen atoms in the core of dislocations as well as in the elastic fields of defects, are modelled by DFT. The structure of the resulting configurations can be rationalised assuming that hydrogen atoms interact elastically with lattice distortions and that they interact between themselves through short-range repulsion. We formulate a two-shell model for hydrogen interaction with an interstitial defect of any size, which predicts how hydrogen accumulates at defects, dislocation loops and line dislocations at a finite temperature. We derive analytical formulae for the number of hydrogen atoms forming the Cottrell atmosphere of a mesoscopic dislocation loop or an edge dislocation. The solubility of hydrogen as a function of temperature, pressure and the density of dislocations exhibits three physically distinct regimes, dominated by the solubility of hydrogen in a perfect lattice, its retention at dislocation cores, and trapping by long-range elastic fields of dislocations.}, - language = {en}, - number = {1}, - urldate = {2020-01-21}, - journal = {Nuclear Fusion}, - author = {Backer, A. De and Mason, D. R. and Domain, C. and Nguyen-Manh, D. and Marinica, M.-C. and Ventelon, L. and Becquart, C. S. and Dudarev, S. L.}, +@book{noauthor_introduction_2013, + address = {New York, NY}, + edition = {1st ed. 2014, Corr. 3rd printing 2016}, + title = {Introduction to {Partial} {Differential} {Equations}}, + isbn = {978-3-319-02098-3}, + abstract = {This textbook is designed for a one year course covering the fundamentals of partial differential equations, geared towards advanced undergraduates and beginning graduate students in mathematics, science, engineering, and elsewhere. The exposition carefully balances solution techniques, mathematical rigor, and significant applications, all illustrated by numerous examples. Extensive exercise sets appear at the end of almost every subsection, and include straightforward computational problems to develop and reinforce new techniques and results, details on theoretical developments and proofs, challenging projects both computational and conceptual, and supplementary material that motivates the student to delve further into the subject.No previous experience with the subject of partial differential equations or Fourier theory is assumed, the main prerequisites being undergraduate calculus, both one- and multi-variable, ordinary differential equations, and basic linear algebra. While the classical topics of separation of variables, Fourier analysis, boundary value problems, Green's functions, and special functions continue to form the core of an introductory course, the inclusion of nonlinear equations, shock wave dynamics, symmetry and similarity, the Maximum Principle, financial models, dispersion and solitons, Huygens'. Principle, quantum mechanical systems, and more make this text well attuned to recent developments and trends in this active field of contemporary research. Numerical approximation schemes are an important component of any introductory course, and the text covers the two most basic approaches: finite differences and finite elements.Furthermore, a Solution Manual for instrucors is available by clicking on "Selected Solutions Manual" under the Additional Information section on the right-hand side of this page. Peter J. Olver is professor of mathematics at the University of Minnesota. His wide-ranging research interests are centered on the development of symmetry-based methods for differential equations and their manifold applications. He is the author of over 130 papers published in major scientific research journals as well as 4 other books, including the definitive Springer graduate text, Applications of Lie Groups to Differential Equations, and another undergraduate text, Applied Linear Algebra.}, + language = {Anglais}, + publisher = {Springer International Publishing AG}, month = nov, - year = {2017}, - pages = {016006}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PPM9WWD9\\Backer et al. - 2017 - Multiscale modelling of the interaction of hydroge.pdf:application/pdf}, + year = {2013}, + file = {2013 - Introduction to Partial Differential Equations.pdf:D\:\\Logiciels\\data_zotero\\storage\\PFU78NHJ\\2013 - Introduction to Partial Differential Equations.pdf:application/pdf}, } -@article{backer_hydrogen_2017, - title = {Hydrogen accumulation around dislocation loops and edge dislocations: from atomistic to mesoscopic scales in {BCC} tungsten}, - volume = {T170}, - issn = {1402-4896}, - shorttitle = {Hydrogen accumulation around dislocation loops and edge dislocations}, - url = {https://doi.org/10.1088%2F1402-4896%2Faa9400}, - doi = {10.1088/1402-4896/aa9400}, - abstract = {In a fusion tokamak, the plasma interacts with the metallic wall and the divertor. Hydrogen isotopes penetrate and diffuse into the material and interact with defects where they are trapped. Neutrons produced by the fusion reactions in the plasma are stopped in the material, creating defects, including vacancy and interstitial clusters, and dislocation loops. The trapping of hydrogen in vacancies has been extensively investigated. In our recent paper (De Backer et al 2017 Nucl. Fusion), we proposed a multi-scale model for H trapping and accumulation around interstitial defects, dislocation loops and dislocation lines. These defects create a long-range elastic field that attracts and may retain H atoms. A two-shell model with a short-range core region and a long-range elastic shell has been parameterized using a database of density functional theory (DFT) calculations. This model gives the number of H atoms forming the Cottrell atmosphere of a defect at finite temperature. In this paper, we present new DFT calculations of large dislocation loops decorated with up to 80 H, and explore our two-shell model in fusion relevant conditions. We conclude that large dislocation loops and edge dislocations can trap a significant number of hydrogen atoms in the core at temperatures up to 800 K, and also in the elastic field if the background hydrogen concentration is high.}, +@book{borthwick_introduction_2016, + address = {Cham}, + series = {Universitext}, + title = {Introduction to {Partial} {Differential} {Equations}}, + isbn = {978-3-319-48934-6 978-3-319-48936-0}, + url = {http://link.springer.com/10.1007/978-3-319-48936-0}, language = {en}, - urldate = {2020-01-21}, - journal = {Physica Scripta}, - author = {Backer, A. De and Mason, D. R. and Domain, C. and Nguyen-Manh, D. and Marinica, M.-C. and Ventelon, L. and Becquart, C. S. and Dudarev, S. L.}, - month = nov, - year = {2017}, - pages = {014073}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\P75275HS\\Backer et al. - 2017 - Hydrogen accumulation around dislocation loops and.pdf:application/pdf}, + urldate = {2020-05-04}, + publisher = {Springer International Publishing}, + author = {Borthwick, David}, + year = {2016}, + doi = {10.1007/978-3-319-48936-0}, + file = {Borthwick - 2016 - Introduction to Partial Differential Equations.pdf:D\:\\Logiciels\\data_zotero\\storage\\8FPDZ3R2\\Borthwick - 2016 - Introduction to Partial Differential Equations.pdf:application/pdf}, } -@article{gao_implementing_2012, - title = {Implementing the {Nelder}-{Mead} simplex algorithm with adaptive parameters}, - volume = {51}, - issn = {1573-2894}, - url = {https://doi.org/10.1007/s10589-010-9329-3}, - doi = {10.1007/s10589-010-9329-3}, - abstract = {In this paper, we first prove that the expansion and contraction steps of the Nelder-Mead simplex algorithm possess a descent property when the objective function is uniformly convex. This property provides some new insights on why the standard Nelder-Mead algorithm becomes inefficient in high dimensions. We then propose an implementation of the Nelder-Mead method in which the expansion, contraction, and shrink parameters depend on the dimension of the optimization problem. Our numerical experiments show that the new implementation outperforms the standard Nelder-Mead method for high dimensional problems.}, +@article{baldwin_experimental_2014, + title = {Experimental study and modelling of deuterium thermal release from {Be}–{D} co-deposited layers}, + volume = {54}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F0029-5515%2F54%2F7%2F073005}, + doi = {10.1088/0029-5515/54/7/073005}, + abstract = {A study of the thermal desorption of deuterium from 1 µm thick co-deposited Be–(0.1)D layers formed at 330 K by a magnetron sputtering technique is reported. A range of thermal desorption rates 0 ⩽ β ⩽ 1.0 K s−1 are explored with a view to studying the effectiveness of the proposed ITER wall and divertor bake procedure (β = 0 K s−1) to be carried out at 513 and 623 K. Fixed temperature bake durations up to 24 h are examined. The experimental thermal release data are used to validate a model input into the Tritium Migration and Analysis Program (TMAP-7). Good agreement with experiment is observed for a TMAP-7 model incorporating trap populations of activation energies for D release of 0.80 and 0.98 eV, and a dynamically computed surface D atomic to molecular recombination rate.}, language = {en}, - number = {1}, - urldate = {2020-01-20}, - journal = {Computational Optimization and Applications}, - author = {Gao, Fuchang and Han, Lixing}, - month = jan, - year = {2012}, - pages = {259--277}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NBQLQII7\\Gao et Han - 2012 - Implementing the Nelder-Mead simplex algorithm wit.pdf:application/pdf}, + number = {7}, + urldate = {2020-04-24}, + journal = {Nuclear Fusion}, + author = {Baldwin, M. J. and Schwarz-Selinger, T. and Doerner, R. P.}, + month = apr, + year = {2014}, + note = {Publisher: IOP Publishing}, + pages = {073005}, + file = {Baldwin et al. - 2014 - Experimental study and modelling of deuterium ther.pdf:D\:\\Logiciels\\data_zotero\\storage\\K2KPP4GX\\Baldwin et al. - 2014 - Experimental study and modelling of deuterium ther.pdf:application/pdf}, } -@article{kelley_detection_1999, - title = {Detection and {Remediation} of {Stagnation} in the {Nelder}–{Mead} {Algorithm} {Using} a {Sufficient} {Decrease} {Condition}}, - volume = {10}, - doi = {10.1137/S1052623497315203}, - abstract = {The Nelder--Mead algorithm can stagnate and converge to a nonoptimal point, even for very simple problems. In this note we propose a test for sufficient decrease which, if passed for all iterations, will guarantee convergence of the Nelder--Mead iteration to a stationary point if the objective function is smooth and the diameters of the Nelder--Mead simplices converge to zero. Failure of this condition is an indicator of potential stagnation. As a remedy we propose a new step, which we call an oriented restart, that reinitializes the simplex to a smaller one with orthogonal edges whose orientation is determined by an approximate descent direction from the current best point. We also give results that apply when the objective function is a low-amplitude perturbation of a smooth function. We illustrate our results with some numerical examples.}, - journal = {SIAM Journal on Optimization}, - author = {Kelley, C. T.}, - year = {1999}, - keywords = {Approximation algorithm, Converge, Descent direction, Iteration, Loss function, Numerical analysis, Numerical method, Optimization problem, Perturbation theory, Stationary process}, - pages = {43--55}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IWHVJUXB\\Kelley - 1999 - Detection and Remediation of Stagnation in the Nel.pdf:application/pdf}, -} +@book{chen_introduction_2016, + address = {Cham}, + title = {Introduction to {Plasma} {Physics} and {Controlled} {Fusion}}, + isbn = {978-3-319-22309-4}, + url = {https://doi.org/10.1007/978-3-319-22309-4_5}, + abstract = {The third edition of this classic text presents a complete introduction to plasma physics and controlled fusion, written by one of the pioneering scientists in this expanding field. It offers both a simple and intuitive discussion of the basic concepts of the subject matter and an insight into the challenging problems of current research. This outstanding text offers students a painless introduction to this important field; for teachers, a large collection of problems; and for researchers, a concise review of the fundamentals as well as original treatments of a number of topics never before explained so clearly. -@book{nocedal_numerical_2006, - address = {New York}, - edition = {2}, - series = {Springer {Series} in {Operations} {Research} and {Financial} {Engineering}}, - title = {Numerical {Optimization}}, - isbn = {978-0-387-30303-1}, - url = {https://www.springer.com/gp/book/9780387303031}, - abstract = {Numerical Optimization presents a comprehensive and up-to-date description of the most effective methods in continuous optimization. It responds to the growing interest in optimization in engineering, science, and business by focusing on the methods that are best suited to practical problems. For this new edition the book has been thoroughly updated throughout. There are new chapters on nonlinear interior methods and derivative-free methods for optimization, both of which are used widely in practice and the focus of much current research. Because of the emphasis on practical methods, as well as the extensive illustrations and exercises, the book is accessible to a wide audience. It can be used as a graduate text in engineering, operations research, mathematics, computer science, and business. It also serves as a handbook for researchers and practitioners in the field. The authors have strived to produce a text that is pleasant to read, informative, and rigorous - one that reveals both the beautiful nature of the discipline and its practical side.}, +In a wholly lucid manner the second edition covered charged-particle motions, plasmas as fluids, kinetic theory, and nonlinear effects. For the third edition, two new chapters have been added to incorporate discussion of more recent advances in the field. The new chapter 9 on Special Plasmas covers non-neutral plasmas, pure electron plasmas, solid and ultra-cold plasmas, pair-ion plasmas, dusty plasmas, helicon plasmas, atmospheric-pressure plasmas, sheath-bounded plasmas, reconnection and turbulence. Following this, chapter 10 describes Plasma Applications such as magnetic fusion (pinches, mirrors, FRCs, stellarators, tokamaks, spheromaks), plasma accelerators and FELs, ine + +rtial fusion, semiconductor etching, and spacecraft propulsion. +This new revised edition remains an essential text for those new to the field and an invaluable reference source for established researchers.}, language = {en}, - urldate = {2020-01-20}, - publisher = {Springer-Verlag}, - author = {Nocedal, Jorge and Wright, S.}, - year = {2006}, - doi = {10.1007/978-0-387-40065-5}, - file = {Nocedal et Wright - 2006 - Numerical Optimization.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ILVMEVZ3\\Nocedal et Wright - 2006 - Numerical Optimization.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZD24XGZZ\\9780387303031.html:text/html}, + urldate = {2020-04-23}, + publisher = {Springer International Publishing}, + author = {Chen, Francis F.}, + editor = {Chen, Francis F.}, + year = {2016}, + doi = {10.1007/978-3-319-22309-4_5}, + file = {Chen - 2016 - Introduction to Plasma Physics and Controlled Fusi.pdf:D\:\\Logiciels\\data_zotero\\storage\\TLNRWWFU\\Chen - 2016 - Introduction to Plasma Physics and Controlled Fusi.pdf:application/pdf}, } -@article{juslin_interatomic_2013, - title = {Interatomic potentials for simulation of {He} bubble formation in {W}}, - volume = {432}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311512003820}, - doi = {10.1016/j.jnucmat.2012.07.023}, - abstract = {A new interatomic pair potential for W–He is described, which includes a short range modification to the Ackland–Thetford tungsten potential. Molecular dynamics simulations using these potentials accurately reproduce ab initio results of the formation energies and ground state positions of He point defects and self interstitial atoms in W. Simulations of larger He–vacancy clusters with up to 20 vacancies and 120 He atoms show strong binding of both He and vacancies to He–vacancy clusters for all cluster sizes. For small clusters, the qualitative agreement with ab initio results is good, although the vacancy binding energy is overestimated by the interatomic potential.}, +@article{esteban_hydrogen_2007, + series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, + title = {Hydrogen transport and trapping in {ODS}-{EUROFER}}, + volume = {82}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379607000580}, + doi = {10.1016/j.fusengdes.2007.02.002}, + abstract = {The gas evolution permeation technique has been used to investigate the interaction of hydrogen with the oxide dispersion strengthened (ODS) reduced activation ferritic–martensitic (RAFM) steel EUROFER. The measurements were performed over the temperature range of 420–777K with hydrogen driving pressures ranging from 2.5×103 to 1.0×105Pa. The resultant diffusive transport parameters are a permeability of Φ (molm−1Pa−1/2s−1)=1.22×10−8exp(−34.6(kJmol−1)/RT), a diffusivity of D (m2s−1)=1.33×10−6exp(−30.4(kJmol−1)/RT) and a Sieverts’ constant of Ks (molm−3Pa−1/2)=9.21×10−3exp(−4.2(kJmol−1)/RT). The resultant trapping parameters have been a trap density of Nt=2.0×1025m−3 and trapping energy of Et=44.9kJmol−1. All the hydrogen transport parameters obtained for the ODS-EUROFER are compared to the available data obtained for the base material EUROFER in order to study the influence of the particular micro-structure of ODS in the hydrogen transport. Other RAFM steels of the same kind are included in the comparative analysis. The presence of yttria nanoparticles induces a marked trapping phenomenon and provokes a decrease in the diffusivity and an increase in the solubility of hydrogen in the material at low temperature.}, language = {en}, - number = {1}, - urldate = {2020-01-15}, - journal = {Journal of Nuclear Materials}, - author = {Juslin, N. and Wirth, B. D.}, - month = jan, - year = {2013}, - keywords = {Molecular dynamics}, - pages = {61--66}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2DJ7CAAR\\Juslin et Wirth - 2013 - Interatomic potentials for simulation of He bubble.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GGGDM3IG\\S0022311512003820.html:text/html}, + number = {15}, + urldate = {2020-04-21}, + journal = {Fusion Engineering and Design}, + author = {Esteban, G. A. and Peña, A. and Legarda, F. and Lindau, R.}, + month = oct, + year = {2007}, + keywords = {Hydrogen, Diffusion, Solubility, Tritium, Fusion reactor materials}, + pages = {2634--2640}, + file = {Esteban et al. - 2007 - Hydrogen transport and trapping in ODS-EUROFER.pdf:D\:\\Logiciels\\data_zotero\\storage\\YD4QEDEW\\Esteban et al. - 2007 - Hydrogen transport and trapping in ODS-EUROFER.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\U2INAZPR\\S0920379607000580.html:text/html}, } -@article{wilson_rare_1974, - title = {Rare gas complexes in tungsten}, - volume = {22}, - issn = {0033-7579}, - url = {https://doi.org/10.1080/00337577408232147}, - doi = {10.1080/00337577408232147}, - abstract = {Specific helium-tungsten defect configurations suggested by Kornelsen to result from ion implantation following irradiation have been calculated. The calculations are atomistic in nature; those interatomic potentials involving the rare gases were determined from fist principles. The divacancy is found to be most stable in the second-neighbor configuration in the pure W lattice, but energetically prefers first-neighbors if it contains a Kr atom. We obtain good agreement with the experimental activation energies although we find certain configurations to differ slightly from those suggested by Kornelsen.}, - number = {1}, - urldate = {2020-01-15}, - journal = {Radiation Effects}, - author = {Wilson, W. D. and Bisson, C. L.}, - month = jan, - year = {1974}, - pages = {63--66}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\F5H4WYSR\\00337577408232147.html:text/html}, +@article{virtanen_scipy_2020, + title = {{SciPy} 1.0: fundamental algorithms for scientific computing in {Python}}, + volume = {17}, + copyright = {2020 The Author(s)}, + issn = {1548-7105}, + shorttitle = {{SciPy} 1.0}, + url = {https://www.nature.com/articles/s41592-019-0686-2}, + doi = {10.1038/s41592-019-0686-2}, + abstract = {This Perspective describes the development and capabilities of SciPy 1.0, an open source scientific computing library for the Python programming language.}, + language = {en}, + number = {3}, + urldate = {2020-04-20}, + journal = {Nature Methods}, + author = {Virtanen, Pauli and Gommers, Ralf and Oliphant, Travis E. and Haberland, Matt and Reddy, Tyler and Cournapeau, David and Burovski, Evgeni and Peterson, Pearu and Weckesser, Warren and Bright, Jonathan and van der Walt, Stéfan J. and Brett, Matthew and Wilson, Joshua and Millman, K. Jarrod and Mayorov, Nikolay and Nelson, Andrew R. J. and Jones, Eric and Kern, Robert and Larson, Eric and Carey, C. J. and Polat, İlhan and Feng, Yu and Moore, Eric W. and VanderPlas, Jake and Laxalde, Denis and Perktold, Josef and Cimrman, Robert and Henriksen, Ian and Quintero, E. A. and Harris, Charles R. and Archibald, Anne M. and Ribeiro, Antônio H. and Pedregosa, Fabian and van Mulbregt, Paul}, + month = mar, + year = {2020}, + note = {Number: 3 +Publisher: Nature Publishing Group}, + pages = {261--272}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YNACZRNV\\Virtanen et al. - 2020 - SciPy 1.0 fundamental algorithms for scientific c.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CGVWUNFW\\s41592-019-0686-2.html:text/html}, } -@article{bergstrom_molecular_2017, - title = {A {Molecular} {Dynamics} {Study} of {Subsurface} {Hydrogen}-{Helium} {Bubbles} in {Tungsten}}, - volume = {71}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST16-121}, - doi = {10.13182/FST16-121}, - abstract = {Fusion reactor materials experience high ion fluxes and operating temperatures, which will ultimately produce subsurface helium and hydrogen bubbles in the tungsten divertor that can cause surface degradation and impact core plasma performance. Molecular dynamics simulations have been used to evaluate the behavior of hydrogen and helium near a 2-nm bubble or void below a tungsten surface as a function of surface orientation, temperature, gas atom concentration, initial hydrogen distribution, and depth below the surface. A clear tendency for hydrogen to segregate to the bubble-matrix interface is observed in these simulations, regardless of the initial spatial distribution of the hydrogen or simulation parameters. This segregation is due in part to a local minimum in the hydrogen energy at the periphery of the bubble. Further work is required to fully characterize the mechanism of this behavior and to assess the quantities of hydrogen in the bubble and at the bubble periphery.}, - number = {1}, - urldate = {2019-10-07}, - journal = {Fusion Science and Technology}, - author = {Bergstrom, Z. J. and Cusentino, M. A. and Wirth, B. D.}, - month = jan, - year = {2017}, - keywords = {Molecular Dynamics, helium bubbles, hydrogen retention, Plasma-surface interactions}, - pages = {122--135}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X64CDL52\\FST16-121.html:text/html;Bergstrom et al. - 2017 - A Molecular Dynamics Study of Subsurface Hydrogen-.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ARFFB7TA\\Bergstrom et al. - 2017 - A Molecular Dynamics Study of Subsurface Hydrogen-.pdf:application/pdf}, +@article{ishikawa_diffusivity_1986, + title = {The diffusivity of hydrogen in aluminum}, + volume = {34}, + issn = {0001-6160}, + url = {http://www.sciencedirect.com/science/article/pii/0001616086902191}, + doi = {10.1016/0001-6160(86)90219-1}, + abstract = {Using an electrolytic method employing a viscous electrolyte, the diffusivity of hydrogen in aluminum has been measured in the temperature range 285–328 K. The results show that H diffuses by a single-stage process from 285 K up to the melting temperature and no departures from Arrhenius behavior due to trapping effects involving lattice vacancies are observed. +Résumé +Nous avons mesuré la diffusivité de l'hydrogène dans l'aluminium entre 285 et 328 K, par une méthode électrolytique utilisant une électrolyte visqueux. Nos résultats montrent que l'hydrogène diffuse par un mécanisme à stade unique de 285 K jusqu'à la température de fusion; l'on n'observe pas d'écart par rapport à un comportement d'Arrhenius, écart qui serait dû à des effets de piègeage mettant en jeu des lacunes. +Zusammenfassung +Mit einer elektrolytischen Methode wurde die Diffusivität von Wasserstoff in Aluminium im Temperaturbereich zwischen 285 und 328 K in einem viskosen Elektrolyten gemessen. Aus den Ergebnissen folgt, daβ H über einen einstufigen Prozeβ zwischen 285 K und der Schmelztemperatur diffundiert. Abweichungen vom Arrhenius-Verhalten durch Einfangeffekte an Gitterleerstellen werden nicht beobachtet.}, + language = {en}, + number = {6}, + urldate = {2020-04-16}, + journal = {Acta Metallurgica}, + author = {Ishikawa, T. and McLellan, R. B.}, + month = jun, + year = {1986}, + pages = {1091--1095}, + file = {Ishikawa et McLellan - 1986 - The diffusivity of hydrogen in aluminum.pdf:D\:\\Logiciels\\data_zotero\\storage\\5FZ75BFB\\Ishikawa et McLellan - 1986 - The diffusivity of hydrogen in aluminum.pdf:application/pdf}, } -@article{becquart_microstructural_2010, - title = {Microstructural evolution of irradiated tungsten: {Ab} initio parameterisation of an {OKMC} model}, - volume = {403}, - issn = {0022-3115}, - shorttitle = {Microstructural evolution of irradiated tungsten}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311510002448}, - doi = {10.1016/j.jnucmat.2010.06.003}, - abstract = {It is important to develop an understanding of the evolution of W microstructure under the conditions expected in the International Thermonuclear Experimental Reactor as well as the DEMOnstration Power Plant, Modelling techniques can be very helpful in this regards. In this paper, an object kinetic Monte Carlo code has been parameterised on ab initio calculations to model the behaviour of helium atoms implanted in tungsten, in the presence or not of the point defects created during the implantation. The slowing down of atomic helium in tungsten as well as the associated Frenkel Pair production is determined using the Marlowe code and is described in a paper companion to this one. The OKMC simulations indicate that He desorption results from a competition between the formation of mobile clusters and sessile ones, and it is thus very important to model correctly their spatial distributions as well as their properties.}, - language = {en}, - number = {1}, - urldate = {2020-01-15}, - journal = {Journal of Nuclear Materials}, - author = {Becquart, C. S. and Domain, C. and Sarkar, U. and DeBacker, A. and Hou, M.}, - month = aug, - year = {2010}, - keywords = {Monte Carlo, Density functional theory}, - pages = {75--88}, - file = {Becquart et al. - 2010 - Microstructural evolution of irradiated tungsten .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FLCG4BYA\\Becquart et al. - 2010 - Microstructural evolution of irradiated tungsten .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GIIXJ4W9\\S0022311510002448.html:text/html}, +@article{drexler_model-based_2019, + title = {Model-based interpretation of thermal desorption spectra of {Fe}-{C}-{Ti} alloys}, + volume = {789}, + issn = {0925-8388}, + url = {http://www.sciencedirect.com/science/article/pii/S0925838819309090}, + doi = {10.1016/j.jallcom.2019.03.102}, + abstract = {A model-based evaluation procedure by a trap-diffusion integrated finite element model (FEM) is used to interpret the experimentally measured thermal desorption spectra (TDS) of Fe-C-Ti alloys. Two material conditions are compared, i.e. as-quenched vs. quenched and tempered, in which TiC have precipitated. The discrepancy between measurement and simulation is found to be very small for all material conditions. The model shows high trapping energies of around 58 kJ/mol to 110 kJ/mol (0.61 eV–1.14 eV), when the materials are tempered. These traps could be related to carbon vacancies in TiC precipitates.}, + language = {en}, + urldate = {2020-04-16}, + journal = {Journal of Alloys and Compounds}, + author = {Drexler, Andreas and Depover, Tom and Verbeken, Kim and Ecker, Werner}, + month = jun, + year = {2019}, + keywords = {A. Alloy, A. Steel, B. Electrochemical calculations, B. Modelling studies, C. Hydrogen embrittlement, C. Stress corrosion}, + pages = {647--657}, + file = {Drexler et al. - 2019 - Model-based interpretation of thermal desorption s.pdf:D\:\\Logiciels\\data_zotero\\storage\\PVI7D4UC\\Drexler et al. - 2019 - Model-based interpretation of thermal desorption s.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QIMRLR8M\\S0925838819309090.html:text/html}, } -@article{xu_modeling_2010, - title = {Modeling spatially dependent kinetics of helium desorption in {BCC} iron following {He} ion implantation}, - volume = {403}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311510002667}, - doi = {10.1016/j.jnucmat.2010.06.025}, - abstract = {One of the most important tasks in fusion materials research is to study the effect of helium on the microstructure and mechanical property evolution of structural materials. Thermal helium desorption spectrometry (THDS), through measuring the outward He surface flux as a function of temperature (or time), provides indirect information about the kinetics and energetics of helium transport and trapping/detrapping which is important for developing a predictive assessment for the life performance of fusion reactors. Nevertheless, THDS data interpretation is not straightforward, particularly when a broad temperature regime and a high He concentration are concerned. Here we present results from a spatially-dependent rate theory modeling framework in coordination with our previous THDS experiments on single crystal iron implanted with 4He+ ions at 5 or 10keV to fluences of 1018 or 1019 He/m2. The model incorporates both temporally and spatially dependent diffusion, trapping, and detrapping (emission) kinetics for both implantation process and post-implantation thermal annealing. Possible desorption sequences/mechanisms are discussed.}, +@article{quiros_blistering_2019, + title = {Blistering and hydrogen retention in poly- and single- crystals of aluminum by a joint experimental-modeling approach}, + volume = {20}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179118301534}, + doi = {10.1016/j.nme.2019.100675}, + abstract = {Aluminum samples have been exposed to a hydrogen plasma generated by a low-pressure – high-density microwave reactor. Aluminum has been chosen as a surrogate for Beryllium. The fluence was kept below 4 × 1024 ions/m2, in order to study the first steps of nucleation and growth of surface and bulk defects, i.e. blisters and bubbles. Experimental analyzes and macroscopic rate equation (MRE) modeling on poly- and single- crystals were made to investigate the role played by grains boundaries in the hydrogen retention. Temperature programmed desorption (TPD) on Al poly-crystals revealed the production of aluminum hydrides (alanes) as majority species in the desorption flux. Comparison of microscopy observations for three different single-crystal orientations (〈100〉, 〈110〉 and 〈111〉) allowed to determine preferential orientations able to attenuate the formation of blisters.}, language = {en}, - number = {1}, - urldate = {2020-01-14}, - journal = {Journal of Nuclear Materials}, - author = {Xu, Donghua and Wirth, Brian D.}, + urldate = {2020-04-16}, + journal = {Nuclear Materials and Energy}, + author = {Quiros, C. and Mougenot, J. and Bisson, R. and Redolfi, M. and Michau, A. and Hassouni, K. and Lombardi, G.}, month = aug, - year = {2010}, - keywords = {Cluster dynamics}, - pages = {184--190}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\AB77726G\\Xu et Wirth - 2010 - Modeling spatially dependent kinetics of helium de.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZUAY4876\\S0022311510002667.html:text/html}, + year = {2019}, + keywords = {Aluminum, Blistering, Hydrogen inventory}, + pages = {100675}, + file = {Quiros et al. - 2019 - Blistering and hydrogen retention in poly- and sin.pdf:D\:\\Logiciels\\data_zotero\\storage\\UEDLCXEF\\Quiros et al. - 2019 - Blistering and hydrogen retention in poly- and sin.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DT387ZRG\\S2352179118301534.html:text/html}, } -@article{ortiz_physically_2004, - title = {A physically based model for the spatial and temporal evolution of self-interstitial agglomerates in ion-implanted silicon}, - volume = {96}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.1786678}, - doi = {10.1063/1.1786678}, - number = {9}, - urldate = {2020-01-14}, - journal = {Journal of Applied Physics}, - author = {Ortiz, Christophe J. and Pichler, Peter and Fühner, Tim and Cristiano, Filadelfo and Colombeau, Benjamin and Cowern, Nicholas E. B. and Claverie, Alain}, +@article{serra_hydrogen_1998, + title = {Hydrogen and deuterium transport and inventory parameters in a {Cu}–0.{65Cr}–0.{08Zr} alloy for fusion reactor applications}, + volume = {258-263}, + issn = {00223115}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0022311598002761}, + doi = {10.1016/S0022-3115(98)00276-1}, + abstract = {A time dependent permeation method has been used to measure the transport and inventory parameters of hydrogen and deuterium in the precipitation hardened (PH) Cu±0.65 wt\% Cr±0.08 wt\% Zr alloy (ELBRODUR HF). The measurements cover the temperature range from 553 to 773 K using a hydrogen or deuterium pressure in the range 1± 100 kPa. The permeabilities, di€usivities and Sieverts' constant values for ELBRODUR obtained in this work were about 2 time higher, 2 times lower and between 3 and 10 time higher respectively to that of Cu (F. Reiter et al., A compilation of Tritium Material Interaction Parameters in Fusion Reactor Materials, EUR 15217 EN (1993)) in the temperature range studied. Using the measured di€usivities and Sieverts' constant values for H2 and D2 and a quantummechanical model, an extrapolation for tritium is also presented. Ó 1998 Elsevier Science B.V. All rights reserved.}, + language = {en}, + urldate = {2020-04-16}, + journal = {Journal of Nuclear Materials}, + author = {Serra, E and Perujo, A}, month = oct, - year = {2004}, - keywords = {Cluster dynamics}, - pages = {4866--4877}, - file = {Ortiz et al. - 2004 - A physically based model for the spatial and tempo.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HIAWGXBI\\Ortiz et al. - 2004 - A physically based model for the spatial and tempo.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\48RZTQ2B\\1.html:text/html}, + year = {1998}, + pages = {1028--1032}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5LM85Y23\\S0022311598002761.html:text/html;Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:D\:\\Logiciels\\data_zotero\\storage\\U6JFAQGI\\Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:application/pdf;Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:D\:\\Logiciels\\data_zotero\\storage\\G96R346E\\Serra et Perujo - 1998 - Hydrogen and deuterium transport and inventory par.pdf:application/pdf}, } -@article{ortiz_he_2007, - title = {He diffusion in irradiated \${\textbackslash}ensuremath\{{\textbackslash}alpha\}{\textbackslash}text\{{\textbackslash}ensuremath\{-\}\}{\textbackslash}mathrm\{{Fe}\}\$: {An} ab-initio-based rate theory model}, - volume = {75}, - shorttitle = {He diffusion in irradiated \${\textbackslash}ensuremath\{{\textbackslash}alpha\}{\textbackslash}text\{{\textbackslash}ensuremath\{-\}\}{\textbackslash}mathrm\{{Fe}\}\$}, - url = {https://link.aps.org/doi/10.1103/PhysRevB.75.100102}, - doi = {10.1103/PhysRevB.75.100102}, - abstract = {The diffusion of He in irradiated α−Fe is studied using a rate theory model addressing the effect of impurities. Ab initio values for the migration and binding energies of He, He-vacancy complexes, vacancy, and self-interstitial clusters are used to model desorption experiments of He-implanted α−Fe. Using the brute ab initio data yields a significant discrepancy with experimental measurements. On the other hand, good agreement is obtained when the vacancy migration energy is increased from the original ab initio value while the binding energies of vacancies with substitutional and interstitial helium are lowered. The presence of impurities, with carbon being the most likely candidate, is proposed as a justification for these effective energies. Our simulations also provide a detailed description of the diffusion mechanisms of He active under these particular experimental conditions.}, - number = {10}, - urldate = {2020-01-14}, - journal = {Physical Review B}, - author = {Ortiz, C. J. and Caturla, M. J. and Fu, C. C. and Willaime, F.}, - month = mar, - year = {2007}, - keywords = {Cluster dynamics}, - pages = {100102}, - file = {APS Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CUP4HCLQ\\PhysRevB.75.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L6DMBTGC\\Ortiz et al. - 2007 - He diffusion in irradiated \$ensuremath alpha te.pdf:application/pdf}, +@article{fernandez_hydrogen_2015, + title = {Hydrogen diffusion and vacancies formation in tungsten: {Density} {Functional} {Theory} calculations and statistical models}, + volume = {94}, + issn = {1359-6454}, + shorttitle = {Hydrogen diffusion and vacancies formation in tungsten}, + url = {http://www.sciencedirect.com/science/article/pii/S1359645415003043}, + doi = {10.1016/j.actamat.2015.04.052}, + abstract = {The interaction of hydrogen with tungsten is investigated by means of the Density Functional Theory (DFT) and statistical methods based on the transition-state theory and thermodynamics. This model yields temperature-dependent data that can help understanding macro-scale experimental results. Within this model, the concentrations of trapped hydrogen atoms at thermodynamic equilibrium are established. Taking into account the configurational entropy, hydrogen is shown to induce vacancy formation below 1000K. Based on this model, TDS spectra are simulated with a basic kinetic model to provide some better insight into the desorption process of hydrogen. Finally, revised mechanisms for hydrogen diffusion in tungsten are proposed; we conclude that the discrepancy existing between the experimental diffusion coefficient measured by Frauenfelder (1969) and the one calculated by DFT would be reconciled provided one uses two different diffusion regimes that would depend on temperature and vacancies concentration.}, + urldate = {2019-10-07}, + journal = {Acta Materialia}, + author = {Fernandez, N. and Ferro, Y. and Kato, D.}, + month = aug, + year = {2015}, + keywords = {Hydrogen, Tungsten, Density Functional Theory, DFT, Nuclear material, Vacancies}, + pages = {307--318}, + file = {Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:D\:\\Logiciels\\data_zotero\\storage\\UIPYD8RG\\Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ICC5AYHS\\Fernandez et al. - 2015 - Hydrogen diffusion and vacancies formation in tung.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VQBUYKST\\S1359645415003043.html:text/html}, } -@article{jourdan_direct_2011, - title = {Direct simulation of resistivity recovery experiments in carbon-doped \${\textbackslash}upalpha\$-iron}, - volume = {T145}, - issn = {1402-4896}, - url = {https://doi.org/10.1088%2F0031-8949%2F2011%2Ft145%2F014049}, - doi = {10.1088/0031-8949/2011/T145/014049}, - abstract = {We present the simulation of resistivity recovery experiments in carbon-doped α-iron over the whole range of temperatures investigated experimentally (from 77 to 600 K). The binding of carbon atoms with both vacancies and self-interstitial atoms has been investigated by density functional theory calculations. The results have then been used in two complementary kinetic models, event-based kinetic Monte Carlo and cluster dynamics, in order to achieve both accuracy and computational efficiency. We show that good agreement is obtained with experiments and that it is possible to identify the elemental mechanisms responsible for the recovery stages.}, +@article{coleman_blueprint_2019, + title = {{BLUEPRINT}: {A} novel approach to fusion reactor design}, + volume = {139}, + issn = {0920-3796}, + shorttitle = {{BLUEPRINT}}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618308019}, + doi = {10.1016/j.fusengdes.2018.12.036}, + abstract = {The European DEMO fusion power reactor (EU-DEMO) is still in the pre-conceptual design phase. The design strategy for the EU-DEMO hinges on investigating multiple reactor designs and technologies in parallel, progressively down-selecting these in the mid-2020s, in preparation for the conceptual design phase. The present implementation of the strategy centres around a baseline single-null design, which is configuration controlled and iterated approximately every two years. The majority of resources are dedicated to studying the baseline design; changing it is expensive, and takes months to do. Competing technologies for different sub-systems (e.g. blankets, magnets) are forced to co-exist within the same physical confines (CAD models), and conform to the same set of performance criteria. Meanwhile, the alternative reactor designs are only loosely defined, with no agreed set of parameters, no CAD models, and no formal framework for study. We argue that the EU-DEMO design strategy is best served by a more efficient implementation methodology which would enable more comprehensive exploration of the DEMO design space. We make the case for a change in approach to the design of DEMO-class reactors in Europe, and propose a solution which bears some resemblance to the present methodology, yet automates and accelerates the sequence of design and analysis activities when generating a design configuration. We present our preliminary attempts to demonstrate the feasibility of our idea, in the form of a new fusion reactor design code: BLUEPRINT. We demonstrate that the typical activities required to generate a DEMO design point can be sped up by four orders of magnitude—from months to minutes—paving the way for a rigorous and broad exploration of the design space.}, language = {en}, - urldate = {2020-01-14}, - journal = {Physica Scripta}, - author = {Jourdan, T. and Fu, Chu Chun and Joly, L. and Bocquet, J. L. and Caturla, M. J. and Willaime, F.}, - month = dec, - year = {2011}, - keywords = {Cluster dynamics}, - pages = {014049}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TINCFAIR\\Jourdan et al. - 2011 - Direct simulation of resistivity recovery experime.pdf:application/pdf}, + urldate = {2020-04-15}, + journal = {Fusion Engineering and Design}, + author = {Coleman, M. and McIntosh, S.}, + month = feb, + year = {2019}, + keywords = {Systems code, DEMO, Fusion reactor, Design}, + pages = {26--38}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\6J99GRHG\\Coleman et McIntosh - 2019 - BLUEPRINT A novel approach to fusion reactor desi.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\D9934YPP\\S0920379618308019.html:text/html}, } -@article{maroudas_helium_2016, - title = {Helium segregation on surfaces of plasma-exposed tungsten}, - volume = {28}, - issn = {0953-8984}, - url = {https://doi.org/10.1088%2F0953-8984%2F28%2F6%2F064004}, - doi = {10.1088/0953-8984/28/6/064004}, - abstract = {We report a hierarchical multi-scale modeling study of implanted helium segregation on surfaces of tungsten, considered as a plasma facing component in nuclear fusion reactors. We employ a hierarchy of atomic-scale simulations based on a reliable interatomic interaction potential, including molecular-statics simulations to understand the origin of helium surface segregation, targeted molecular-dynamics (MD) simulations of near-surface cluster reactions, and large-scale MD simulations of implanted helium evolution in plasma-exposed tungsten. We find that small, mobile He n (1 ⩽ n ⩽ 7) clusters in the near-surface region are attracted to the surface due to an elastic interaction force that provides the thermodynamic driving force for surface segregation. This elastic interaction force induces drift fluxes of these mobile He n clusters, which increase substantially as the migrating clusters approach the surface, facilitating helium segregation on the surface. Moreover, the clusters’ drift toward the surface enables cluster reactions, most importantly trap mutation, in the near-surface region at rates much higher than in the bulk material. These near-surface cluster dynamics have significant effects on the surface morphology, near-surface defect structures, and the amount of helium retained in the material upon plasma exposure. We integrate the findings of such atomic-scale simulations into a properly parameterized and validated spatially dependent, continuum-scale reaction-diffusion cluster dynamics model, capable of predicting implanted helium evolution, surface segregation, and its near-surface effects in tungsten. This cluster-dynamics model sets the stage for development of fully atomistically informed coarse-grained models for computationally efficient simulation predictions of helium surface segregation, as well as helium retention and surface morphological evolution, toward optimal design of plasma facing components.}, +@article{roth_tritium_2008, + title = {Tritium inventory in {ITER} plasma-facing materials and tritium removal procedures}, + volume = {50}, + issn = {0741-3335}, + url = {https://doi.org/10.1088%2F0741-3335%2F50%2F10%2F103001}, + doi = {10.1088/0741-3335/50/10/103001}, + abstract = {Interactions between the plasma and the vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining the choice of the plasma-facing materials. A prominent issue in this choice is the tritium inventory build-up in the vessel, which must be limited for safety reasons. The initial material selection, i.e. beryllium (Be) on the main vessel walls, tungsten (W) on the divertor upper baffle and dome, and carbon fibre composite around the strike points on the divertor plates, results both from the attempt to reduce the tritium inventory and to optimize the lifetime of the plasma-facing components.In the framework of the EU Task Force on Plasma–Wall Interaction (PWI TF), the many physics aspects governing the tritium inventory are brought together. Together with supporting information from international experts represented by the ITPA SOL/DIV section, this paper describes the present status of knowledge of the in-vessel tritium inventory build-up. Firstly, the main results from present fusion devices in this field are briefly reviewed. Then, the processes involved are discussed: implantation, trapping and diffusion in plasma-facing materials are considered as well as surface erosion and co-deposition of tritium with eroded material. The intermixing of the different materials and its influence on hydrogen retention and co-deposition is a major source of uncertainty on present estimates and is also addressed.Based on the previous considerations, estimates for the tritium inventory build-up are given for the initial choice of ITER materials, as well as for alternative options. Present estimates indicate a build-up of the tritium inventory to the administrative limit within a few hundred nominal full power D : T discharges, co-deposition with carbon being the dominant process. Therefore, tritium removal methods are also an active area of research within the EU PWI TF, and are discussed. An integrated operational scheme to slow the rate of tritium accumulation is presented, which includes plasma operation as well as conditioning procedures.}, language = {en}, - number = {6}, - urldate = {2020-01-14}, - journal = {Journal of Physics: Condensed Matter}, - author = {Maroudas, Dimitrios and Blondel, Sophie and Hu, Lin and Hammond, Karl D. and Wirth, Brian D.}, - month = jan, - year = {2016}, - pages = {064004}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SFKLHLKE\\Maroudas et al. - 2016 - Helium segregation on surfaces of plasma-exposed t.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MAUQ4VWI\\pdf.html:text/html}, + number = {10}, + urldate = {2020-04-14}, + journal = {Plasma Physics and Controlled Fusion}, + author = {Roth, Joachim and Tsitrone, Emmanuelle and Loarer, Thierry and Philipps, Volker and Brezinsek, Sebastijan and Loarte, Alberto and Counsell, Glenn F. and Doerner, Russell P. and Schmid, Klaus and Ogorodnikova, Olga V. and Causey, Rion A.}, + month = aug, + year = {2008}, + note = {Publisher: IOP Publishing}, + pages = {103001}, + file = {Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:D\:\\Logiciels\\data_zotero\\storage\\IIBT4U4N\\Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:application/pdf;Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:D\:\\Logiciels\\data_zotero\\storage\\V8VT5QFS\\Roth et al. - 2008 - Tritium inventory in ITER plasma-facing materials .pdf:application/pdf}, } -@article{li_accumulation_2012, - title = {The {Accumulation} of {He} on a {W} {Surface} {During} {keV}-{He} {Irradiation}: {Cluster} {Dynamics} {Modeling}}, - volume = {14}, - issn = {1009-0630}, - shorttitle = {The {Accumulation} of {He} on a {W} {Surface} {During} {keV}-{He} {Irradiation}}, - url = {https://doi.org/10.1088%2F1009-0630%2F14%2F7%2F13}, - doi = {10.1088/1009-0630/14/7/13}, - abstract = {The accumulation of He on a W surface during keV-He ion irradiation has been simulated using cluster dynamics modeling. This is based mainly on rate theory and improved by involving different types of objects, adopting up-to-date parameters and complex reaction processes, as well as considering the diffusion process along with depth. These new features make the simulated results compare very well with the experimental ones. The accumulation and diffusion processes are analyzed, and the depth and size dependence of the He concentrations contributed by different types of He clusters is also discussed. The exploration of the trapping and diffusion effects of the He atoms is helpful in understanding the evolution of the damages in the near-surface of plasma-facing materials under He ion irradiation.}, +@article{hirai_use_2016, + title = {Use of tungsten material for the {ITER} divertor}, + volume = {9}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179115301046}, + doi = {10.1016/j.nme.2016.07.003}, + abstract = {Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R\&D for high performance armor-heat sink joint were necessary to be implemented. In the R\&D, the availability of the technology was demonstrated by high heat flux test of tungsten monoblock components. Not systematically but frequently macro-cracks appeared at the middle of monoblocks after 20MW/m2 loading. The initiation of such macro-cracks was considered to be due to cyclic exposure to high temperature, ∼2000°C, where creep, recrystallization and low cycle fatigue were concerned. To understand correlation between the macro-crack appearance and mechanical properties and possible update of acceptance criteria in the material specification, an activity to characterize the tungsten monoblocks was launched.}, language = {en}, - number = {7}, - urldate = {2020-01-10}, - journal = {Plasma Science and Technology}, - author = {Li, Yonggang and Zhou, Wanghuai and Huang, Liangfeng and Ning, Ronghui and Zeng, Zhi and Ju, Xin}, - month = jul, - year = {2012}, - keywords = {Cluster dynamics}, - pages = {624--628}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7CDKDCBE\\Li et al. - 2012 - The Accumulation of He on a W Surface During keV-H.pdf:application/pdf}, + urldate = {2020-04-12}, + journal = {Nuclear Materials and Energy}, + author = {Hirai, T. and Panayotis, S. and Barabash, V. and Amzallag, C. and Escourbiac, F. and Durocher, A. and Merola, M. and Linke, J. and Loewenhoff, Th. and Pintsuk, G. and Wirtz, M. and Uytdenhouwen, I.}, + month = dec, + year = {2016}, + pages = {616--622}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\X95BBN5J\\Hirai et al. - 2016 - Use of tungsten material for the ITER divertor.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DUQXP5GH\\S2352179115301046.html:text/html}, } -@article{hu_synergistic_2014, - title = {Synergistic effect of helium and hydrogen for bubble swelling in reduced-activation ferritic/martensitic steel under sequential helium and hydrogen irradiation at different temperatures}, - volume = {89}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379614001173}, - doi = {10.1016/j.fusengdes.2014.02.033}, - abstract = {In order to investigate the synergistic effect of helium and hydrogen on swelling in reduced-activation ferritic/martensitic (RAFM) steel, specimens were separately irradiated by single He+ beam and sequential He+ and H+ beams at different temperatures from 250 to 650°C. Transmission electron microscope observation showed that implantation of hydrogen into the specimens pre-irradiated by helium can result in obvious enhancement of bubble size and swelling rate which can be regarded as a consequence of hydrogen being trapped by helium bubbles. But when temperature increased, Ostwald ripening mechanism would become dominant, besides, too large a bubble could become mobile and swallow many tiny bubbles on their way moving, reducing bubble number density. And these effects were most remarkable at 450°C which was the peak bubble swelling temperature for RAMF steel. When temperature was high enough, say above 450, point defects would become mobile and annihilate at dislocations or surface. As a consequence, helium could no longer effectively diffuse and clustering in materials and bubble formation was suppressed. When temperature was above 500, helium bubbles would become unstable and decompose or migrate out of surface. Finally no bubble was observed at 650°C.}, - language = {en}, - number = {4}, - urldate = {2020-01-10}, - journal = {Fusion Engineering and Design}, - author = {Hu, Wenhui and Guo, Liping and Chen, Jihong and Luo, Fengfeng and Li, Tiecheng and Ren, Yaoyao and Suo, Jinping and Yang, Feng}, - month = apr, - year = {2014}, - keywords = {Helium bubbles, Helium/hydrogen synergistic effect, Reduced-activation ferritic/martensitic steel, Swelling}, - pages = {324--328}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PDIX4N9W\\Hu et al. - 2014 - Synergistic effect of helium and hydrogen for bubb.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PYIPCGQ2\\S0920379614001173.html:text/html}, +@phdthesis{dolan_tritium_2021, + type = {Thesis}, + title = {Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor}, + copyright = {MIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided.}, + url = {https://dspace.mit.edu/handle/1721.1/131004}, + abstract = {Advanced reactor concepts which use a lithium- or beryllium-bearing primary salt coolant will require technical solutions to mitigate the environmental release of tritium. One such design is the Fluoride-Salt-Cooled High-Temperature Reactor (FHR), which combines a molten Flibe (2LiF-BeF₂) salt coolant and tri-structural isotropic coated-particle fuel to produce power or process heat. Compared to current water-cooled reactors, managing tritium release from a FHR is further complicated by the mobility of tritium at high temperatures and limited knowledge of interactions between tritium and nuclear graphite in the molten fluoride salt environment. The total activity, chemical forms, and retention mechanisms for tritium in nuclear graphite were studied through thermal desorption analysis of sample materials from three in-core Flibe salt irradiations (denoted FS-1, FS-2, and FS-3) at the MIT Reactor (MITR).}, + language = {eng}, + urldate = {2021-07-08}, + school = {Massachusetts Institute of Technology}, + author = {Dolan, Kieran Patrick}, + year = {2021}, + note = {Accepted: 2021-06-17T17:21:11Z}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\NFSWCSCT\\Dolan - 2021 - Tritium retention in nuclear graphite, system-leve.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TXMLRMJM\\131004.html:text/html}, } -@article{mccarthy_enhanced_2020, - title = {Enhanced fuzzy tungsten growth in the presence of tungsten deposition}, - volume = {60}, - issn = {0029-5515}, - url = {https://doi.org/10.1088%2F1741-4326%2Fab6060}, - doi = {10.1088/1741-4326/ab6060}, - abstract = {Using a magnetron sputtering device operating in helium, fibre-form ‘fuzz’ has been grown on tungsten samples in the presence of a significant auxiliary source of depositing tungsten. In this system, fuzzy tungsten was grown over a range of helium ion fluences, , sample temperatures and helium ion energies, but with operator control over the tungsten atom-to-helium ion arrival rate ratio at the sample (from 0.003 to 0.009). In the presence of tungsten deposition, it appears that the fuzz growth has two distinct stages: at low to intermediate helium ion fluence the fuzzy layer thickness follows the expected diffusive law augmented by approximately the ‘effective’ thin film thickness of deposited tungsten; at high fluences the fuzz thickness increases very steeply with . These observations are explained through the increase in the porosity of the fuzzy layer as it reaches thicknesses larger than ∼1 m. It was observed that during the second phase of fuzz growth the thickness was highly dependent on both the sample temperature and the tungsten atom-to-helium ion arrival rate ratio. For the same helium ion exposure, an increase in the sample temperature from 1050 to 1150 K lead to a six-fold increase in the fuzzy layer thickness, whilst increasing the tungsten atom-to-helium ion arrival rate ratio over the full range produced a two-fold increase in the thickness. Microscopy and electron diffraction studies of the grown structures show clearly helium bubbles within polycrystalline tendrils.}, +@article{zaloznik_deuterium_2020, + title = {Deuterium removal from beryllium co-deposits by simulated strike-point sweeping}, + volume = {24}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179120300260}, + doi = {10.1016/j.nme.2020.100750}, + abstract = {Beryllium (Be) co-deposition with hydrogen isotopes will probably be the main mechanism of tritium accumulation in ITER. To reduce the use of baking of the first wall and divertor, raising strike-points during a pure deuterium (D) discharge has been proposed to heat the co-deposits directly and enhance tritium desorption. The feasibility of such plasma-induced removal as a potential means of tritium control has been investigated. Be-D co-deposited layers with a thickness of around 3 μm were created at 428–458 K and exposed to D or H plasma at various temperatures (673–873 K) for various times (180–1200 s). The remaining D content was measured by thermal desorption spectroscopy and compared to the control samples. Plasma-induced desorption was found to be efficient in removing significant amounts of D out of the co-deposits, removing 85\% of D from the layer after D plasma exposure at 773 K for 1200 s and 84\% of D after exposure at 873 K for only 180 s.}, language = {en}, - number = {2}, - urldate = {2020-01-09}, - journal = {Nuclear Fusion}, - author = {McCarthy, Patrick and Hwangbo, Dogyun and Bilton, Matthew and Kajita, Shin and Bradley, James W.}, - month = jan, + urldate = {2021-06-29}, + journal = {Nuclear Materials and Energy}, + author = {Založnik, Anže and Doerner, Russell P. and De Temmerman, Gregory}, + month = aug, year = {2020}, - keywords = {Fuzz}, - pages = {026012}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\V9QTPMN2\\McCarthy et al. - 2020 - Enhanced fuzzy tungsten growth in the presence of .pdf:application/pdf}, + keywords = {Deuterium, Beryllium co-deposits, Tritium removal}, + pages = {100750}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\VZEWE7VS\\Založnik et al. - 2020 - Deuterium removal from beryllium co-deposits by si.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5H2UMUJF\\S2352179120300260.html:text/html}, } -@article{liu_new_2018, - title = {New helium bubble growth mode at a symmetric grain-boundary in tungsten: accelerated molecular dynamics study}, - volume = {6}, - issn = {null}, - shorttitle = {New helium bubble growth mode at a symmetric grain-boundary in tungsten}, - url = {https://doi.org/10.1080/21663831.2018.1494637}, - doi = {10.1080/21663831.2018.1494637}, - abstract = {This work, with an emphasis on helium irradiation rates appropriate for fusion-plasma conditions, advances the understanding of helium evolution at grain boundaries in W, an important consideration in the understanding of W as a plasma-facing component. Using accelerated molecular dynamics, helium bubble nucleation and growth at a symmetric Σ5[100](310) tilt grain-boundary in W is studied. The simulations reveal that the growth mode associated with bubble growth at the grain-boundary leads to a suppression of the helium supply to the bubble and hence to arrested growth. Such an unconventional bubble growth mode may dominate in materials with a high density of sinks.}, - number = {9}, - urldate = {2020-01-08}, - journal = {Materials Research Letters}, - author = {Liu, X.-Y. and Uberuaga, B. P. and Perez, D. and Voter, A. F.}, - month = sep, - year = {2018}, - keywords = {Molecular Dynamics}, - pages = {522--530}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7YICGIPV\\21663831.2018.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Y7THBY4U\\Liu et al. - 2018 - New helium bubble growth mode at a symmetric grain.pdf:application/pdf}, +@article{kuang_divertor_2020, + title = {Divertor heat flux challenge and mitigation in {SPARC}}, + volume = {86}, + issn = {0022-3778, 1469-7807}, + url = {https://www.cambridge.org/core/journals/journal-of-plasma-physics/article/divertor-heat-flux-challenge-and-mitigation-in-sparc/A25A8CFADBBA33AD9AAC18F24E40A18E}, + doi = {10.1017/S0022377820001117}, + abstract = {Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m−2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections ({\textasciitilde}11–34 MJ m−2) are comparable with those for ITER. However, the relatively short pulse length ({\textasciitilde}25 s pulse, with a {\textasciitilde}10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a {\textasciitilde}1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.}, + language = {en}, + number = {5}, + urldate = {2021-06-28}, + journal = {Journal of Plasma Physics}, + author = {Kuang, A. Q. and Ballinger, S. and Brunner, D. and Canik, J. and Creely, A. J. and Gray, T. and Greenwald, M. and Hughes, J. W. and Irby, J. and LaBombard, B. and Lipschultz, B. and Lore, J. D. and Reinke, M. L. and Terry, J. L. and Umansky, M. and Whyte, D. G. and Wukitch, S. and Team, the SPARC}, + month = oct, + year = {2020}, + note = {Publisher: Cambridge University Press}, + keywords = {fusion plasma, plasma devices}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ZYVDDGA2\\Kuang et al. - 2020 - Divertor heat flux challenge and mitigation in SPA.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\JDTJ42TK\\A25A8CFADBBA33AD9AAC18F24E40A18E.html:text/html}, } -@article{nguyen_modeling_2019, - title = {Modeling the effects of helium-vacancy clusters on the stress-strain response of a grain boundary in iron by a mechanistic finite element approach informed by molecular dynamics data}, - volume = {526}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311519304106}, - doi = {10.1016/j.jnucmat.2019.151766}, - abstract = {The effects of helium (He)-vacancy clusters on the stress-strain behavior of polycrystalline iron (α-Fe) are investigated by a mechanistic finite element (FE) approach using a continuum damage mechanics (CDM) description of the material behavior informed by molecular dynamics (MD) data. First, MD analyses of a single crystal (loading normal to \{332\} plane) and a bicrystal system containing a Σ11{\textless}110{\textgreater}\{332\} grain boundary (GB) were performed to compute the uniaxial tensile response of an Fe single crystal and a system with a GB. MD results were then used in FE analyses of the same systems to identify parameters for the CDM constitutive relations for the crystal and the traction-separation law for the GB depicted by cohesive elements. Next, a 3D FE model of an α-Fe bicrystal system with an imperfect GB subjected to uniaxial tensile loading was developed. This model includes an equivalent hollow sphere under internal pressure in the middle of the GB to model the effects of pressurized He bubbles at 5 K, room temperature (RT) and 600 K on stress, strain and damage distributions. The radius of the equivalent sphere was determined assuming the presence of two vacancies in the system. Finally, MD stress/strain data of the same bicrystal system with He-vacancy clusters were compared to the corresponding FE results to validate this mechanistic approach that appears to be efficient in terms of computational time. FE model predictions of system strength and fracture strain are in fairly good agreement with the MD results at all three temperatures. Our results show that small and highly pressurized He-vacancy clusters reduce GB strength and fracture strain more significantly at 5 K than at RT and 600 K.}, +@article{lasa_multi-physics_2020, + title = {Multi-physics modeling of the long-term evolution of helium plasma exposed surfaces}, + volume = {T171}, + issn = {1402-4896}, + url = {https://doi.org/10.1088/1402-4896/ab4c29}, + doi = {10.1088/1402-4896/ab4c29}, + abstract = {In this manuscript we introduce a simulation tool-suite for predicting plasma-surface interactions (PSI), which aims to predict the evolution of the plasma-facing surfaces that continually change due to exposure to fusion plasmas. A comprehensive description of PSI involves a wide range of physical phenomena, of which we include components for (a) the gas implantation and its dynamic evolution below the divertor surface; (b) erosion of wall material; (c) transport and re-deposition of the eroded impurities; and (d) the scrape-off layer plasma including fuel ions and extrinsic impurities. These components are integrated to predict changes in surface morphology and fuel recycling, and the effect of material erosion and re-deposition in fuel retention. Integrated simulations for ITER-like parameters in a helium plasma environment are presented, focused on the response of the tungsten divertor. The model is also applied to predicting the response of the tungsten surface pre-damaged by He plasma, to burning plasma operations. This case further demonstrates the capability to model the effect of sub-surface helium dynamics, which include helium nucleation, clustering and the bursting of over-pressurized bubbles, its impact on fuel recycling as well as the effect of sputtering on the surface evolution.}, language = {en}, - urldate = {2020-01-08}, - journal = {Journal of Nuclear Materials}, - author = {Nguyen, Ba Nghiep and Kurtz, Richard J. and Gao, Fei}, - month = dec, - year = {2019}, - keywords = {Molecular Dynamics}, - pages = {151766}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FR2SI8JU\\Nguyen et al. - 2019 - Modeling the effects of helium-vacancy clusters on.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SRASH3CL\\S0022311519304106.html:text/html}, + urldate = {2021-06-25}, + journal = {Physica Scripta}, + author = {Lasa, A. and Canik, J. M. and Blondel, S. and Younkin, T. R. and Curreli, D. and Drobny, J. and Roth, P. and Cianciosa, M. and Elwasif, W. and Green, D. L. and Wirth, B. D.}, + month = jan, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {014041}, + file = {Lasa et al. - 2020 - Multi-physics modeling of the long-term evolution .pdf:D\:\\Logiciels\\data_zotero\\storage\\WRQRYH85\\Lasa et al. - 2020 - Multi-physics modeling of the long-term evolution .pdf:application/pdf}, } -@article{lhuillier_trapping_2011, - series = {Nuclear {Materials} {IV}}, - title = {Trapping and release of helium in tungsten}, - volume = {416}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311510008640}, - doi = {10.1016/j.jnucmat.2010.12.042}, - abstract = {The behavior of tungsten under irradiation and helium implantation is a major stake of the material-related issues of fusion reactors. In this perspective the fate of helium in tungsten was studied by mean of several characterization techniques. The aim of this study is to highlight the trapping mechanisms of helium in tungsten and their correlation with implantation-induced defects. Helium was implanted into tungsten at two different energies, 0.32 and 60keV. The helium was studied as a function of temperature by using nuclear reaction analysis. The migration propensity of helium was correlated with the release rate of helium after annealing at a given temperature. In addition, the helium trapping sites and evolution with post-implantation annealing was investigated using Doppler-Broadening Positron Annihilation Spectroscopy. It has been shown that the release, and so the migration, of helium is guided by the concentration of implantation-induced defects and the nature of the helium traps created during the implantation.}, +@book{reiter_compilation_1996, + title = {A compilation of tritium : {Material} interaction parameters in fusion reactor materials.}, + shorttitle = {A compilation of tritium}, + abstract = {Details of the publication}, language = {en}, - number = {1}, - urldate = {2020-01-08}, - journal = {Journal of Nuclear Materials}, - author = {Lhuillier, P. E. and Belhabib, T. and Desgardin, P. and Courtois, B. and Sauvage, T. and Barthe, M. F. and Thomann, A. L. and Brault, P. and Tessier, Y.}, - month = sep, - year = {2011}, - pages = {13--17}, - file = {Lhuillier et al. - 2011 - Trapping and release of helium in tungsten.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6P5R4R4K\\Lhuillier et al. - 2011 - Trapping and release of helium in tungsten.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\AJUXVRFY\\S0022311510008640.html:text/html}, + urldate = {2020-04-16}, + publisher = {Publications Office of the European Union}, + author = {Reiter, F. and Forcey, K. S. and Gervasini, G.}, + month = jul, + year = {1996}, + file = {Union - 1996 - A compilation of tritium Material interaction pa.pdf:D\:\\Logiciels\\data_zotero\\storage\\B3DLFNWI\\Union - 1996 - A compilation of tritium Material interaction pa.pdf:application/pdf}, } -@article{moller_dynamic_2016, - title = {Dynamic outgassing of deuterium, helium and nitrogen from plasma-facing materials under {DEMO} relevant conditions}, - volume = {57}, +@article{kaveeva_solps-iter_2020, + title = {{SOLPS}-{ITER} modelling of {ITER} edge plasma with drifts and currents}, + volume = {60}, issn = {0029-5515}, - url = {https://doi.org/10.1088%2F0029-5515%2F57%2F1%2F016020}, - doi = {10.1088/0029-5515/57/1/016020}, - abstract = {In confined plasma magnetic fusion devices significant amounts of the hydrogen isotopes used for the fusion reaction can be stored in the plasma-facing materials by implantation. The desorption of this retained hydrogen was seen to follow a t α law with α ≈ −0.7 in tokamaks. For a pulsed fusion reactor this outgassing can define the inter-pulse waiting time. This work presents new experimental data on the dynamic outgassing in ITER grade tungsten exposed under the well-defined conditions of PSI-2 to pure and mixed D2 plasmas. A peak ion flux of 1022 D+ m−2 s is applied for up to 6 h at sample temperatures of up to 900 K. Pure D2 and mixed D2 + He, D2 + N2 and D2 + He + N2 plasmas are applied to the sample at 68 V bias. The D2, He, N outgassing at 293 K and 580 k are observed via in-vacuo quadrupole mass spectrometry covering the range of 40 s–200 000 s after exposure. The outgassing decay follows a single power law with exponents α = −0.7 to −1.1 at 293 K, but at 580 K a drop from α = −0.25 to −2.35 is found. For DEMO a pump-down time to 0.5 mPa in the order of 1–5 h can be expected. The outgassing is in all cases dominated by D2.}, + url = {https://doi.org/10.1088/1741-4326/ab73c1}, + doi = {10.1088/1741-4326/ab73c1}, + abstract = {Using the new version of the SOLPS plasma boundary code package, SOLPS-ITER, this paper presents the first ever simulations of the ITER burning baseline H-mode edge plasma with drifts and currents activated. Neon (Ne) seeded discharges for divertor power dissipation are considered. The results for divertor and scrape-off layer (SOL) parameters with and without drifts are compared, both for the SOLPS-ITER simulations and against the earlier SOLPS-4.3 modelling (which did not include a drift description) constituting the bulk of the existing ITER divertor simulation database. Whereas the drift effect on the equatorial midplane (main chamber) density and temperature profiles is moderate, drifts increase the peak heat flow to the outer divertor target. This effect is more pronounced for regimes with low sub-divertor neutral pressure, when even drift-free SOLPS4.3 simulations find strong out-in target power asymmetries. An important conclusion is thus that if ITER operates as expected with partially detached divertor targets, drifts should not influence the power handling, but that in the case of divertor reattachment, they will act to worsen the target loading, increasing the need for development of reliable schemes for detachment control. Comparing SOLPS-4.3 and SOLPS-ITER results for the key peak target heat flux versus sub-divertor neutral pressure operating domain, SOLPS-ITER with drifts predicts a narrower operational window for the divertor pressure.}, language = {en}, - number = {1}, - urldate = {2020-01-08}, + number = {4}, + urldate = {2021-06-21}, journal = {Nuclear Fusion}, - author = {Möller, S. and Matveev, D. and Martynova, Y. and Unterberg, B. and Rasinski, M. and Wegener, T. and Kreter, A. and Linsmeier, Ch}, - month = nov, - year = {2016}, - pages = {016020}, - file = {Möller et al. - 2016 - Dynamic outgassing of deuterium, helium and nitrog.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NMFVVGTN\\Möller et al. - 2016 - Dynamic outgassing of deuterium, helium and nitrog.pdf:application/pdf}, + author = {Kaveeva, E. and Rozhansky, V. and Senichenkov, I. and Sytova, E. and Veselova, I. and Voskoboynikov, S. and Bonnin, X. and Pitts, R. A. and Kukushkin, A. S. and Wiesen, S. and Coster, D.}, + month = mar, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {046019}, } -@article{das_hardening_2019, - title = {Hardening and {Strain} {Localisation} in {Helium}-{Ion}-{Implanted} {Tungsten}}, - volume = {9}, - issn = {2045-2322}, - url = {http://www.nature.com/articles/s41598-019-54753-3}, - doi = {10.1038/s41598-019-54753-3}, +@article{park_assessment_2020, + title = {Assessment of {ITER} divertor performance during early operation phases}, + volume = {61}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/abc1ce}, + doi = {10.1088/1741-4326/abc1ce}, + abstract = {During the ITER design phase, the focus of ITER boundary plasma modeling activities has been on divertor performance under baseline H-mode, fusion power operation (FPO) conditions. However, early ITER operation will be primarily with hydrogen fuel in L-mode, in the pre-fusion power operation 1 (PFPO-1) phase. Here, the SOLPS-ITER code is used to evaluate divertor performance during this non-active phase. To verify the assumptions used in the existing high power simulation database, gas throughput scans were performed for two types of divertor surface material (beryllium and tungsten) and two gas puff locations (divertor and main chamber). The adoption of beryllium target surfaces simulates the effect of main chamber material erosion and migration and, along with main chamber gas injection, is the current default for the high power database. Depending on the divertor surface material, the atom to molecule ratio of the recycled neutral particles varies. This modifies the momentum and power loss mechanisms arising from plasma–neutral interactions. However, since the effect of atomic and molecular reactions are compensatory, the ‘total’ power and momentum losses are relatively insensitive to the target surface material. Similarly, the impact of gas puff location on divertor plasma parameters is not significant, though main chamber injection provides an additional ionization source in the upstream scrape-off layer (SOL) and leads to moderate changes in the upstream density and far SOL parameters. However, these effects can be neglected within the available range of the gas puff and pump rates in ITER. Since beryllium and tungsten are materials at both extremes in terms of surface reflection properties, the conclusions may be applicable to other divertor surface materials. An important additional finding of the study is that the insensitivity of upstream density to divertor neutral pressure found in the FPO database is also recovered in these PFPO-1 simulations.}, language = {en}, number = {1}, - urldate = {2020-01-08}, - journal = {Scientific Reports}, - author = {Das, Suchandrima and Yu, Hongbing and Tarleton, Edmund and Hofmann, Felix}, + urldate = {2021-06-21}, + journal = {Nuclear Fusion}, + author = {Park, Jae-Sun and Bonnin, Xavier and Pitts, Richard}, month = dec, - year = {2019}, - pages = {18354}, - file = {Das et al. - 2019 - Hardening and Strain Localisation in Helium-Ion-Im.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\M9XNW9YG\\Das et al. - 2019 - Hardening and Strain Localisation in Helium-Ion-Im.pdf:application/pdf}, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {016021}, } -@article{dunn_rate_2013, - title = {A rate theory study of helium bubble formation and retention in {Cu}–{Nb} nanocomposites}, - volume = {435}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311512006988}, - doi = {10.1016/j.jnucmat.2012.12.041}, - abstract = {A spatially dependent rate theory model for helium migration, clustering, and trapping on interfaces between Cu and Nb layers is introduced to predict the evolution of the concentrations of He clusters of various sizes during implantation and early annealing. Migration and binding energies of point defects and small clusters in bulk Cu and Nb are found using conjugate gradient minimization and the nudged elastic band method. This model is implemented in a three-dimensional framework and used to predict the relationship between helium bubble formation and the nano-composite microstructure, including interfacial free volume, grain size, and layer thickness. Interstitial and vacancy-like migration of helium is considered. The effects of changing layer thickness and interfacial misfit dislocation density on the threshold for helium bubble nucleation are found to match experiments. Accelerated helium release due to interfaces and grain boundaries is shown to occur only when diffusion rates on interfaces and grain boundaries are greatly increased relative to the bulk material.}, +@article{fan_impact_2021, + title = {Impact of helium irradiation on the crystallographic orientation change in single-crystalline tungsten {\textbackslash}ast}, + volume = {61}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/abff04}, + doi = {10.1088/1741-4326/abff04}, + abstract = {Understanding the helium effects on the surface modifications of tungsten is of great interest and significance for developing plasma-facing materials. Our recent studies revealed that the ion irradiation of helium at room temperature produces 〈111〉-oriented surface grains in single-crystalline tungsten 100 and 110, which may play an important role in the surface and subsurface evolutions of tungsten subjected to fusion-relevant service environments. Although the driving force for the formation of surface grains is well explained by ion channeling effect, the underlying formation mechanism remains unclear. In this work, we investigated the orientation relationship between irradiation-induced new surface grains and single-crystalline tungsten matrix. The experimental results of electron backscatter diffraction demonstrated that the formation of most 〈111〉-oriented surface grains in both helium-irradiated tungsten 100 or 110 can be regarded as the grain rotation of matrix around its in-plane 〈110〉 axis.}, language = {en}, - number = {1}, - urldate = {2020-01-08}, - journal = {Journal of Nuclear Materials}, - author = {Dunn, A. Y. and McPhie, M. G. and Capolungo, L. and Martinez, E. and Cherkaoui, M.}, - month = apr, - year = {2013}, - keywords = {Finite Element}, - pages = {141--152}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4DAREWU8\\Dunn et al. - 2013 - A rate theory study of helium bubble formation and.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\J5Q3MQGG\\S0022311512006988.html:text/html}, -} - -@phdthesis{faney_numerical_2013, - title = {Numerical {Simulations} of {Tungsten} under {Helium} {Irradiation}}, - abstract = {Magnetic confinement fusion is a promising technology for electricity production due to available fuel and low waste products. However, the construction of a nuclear fusion reactor remains -a scientific challenge. One of the main issues is the resistance of the plasma facing materials exposed to very harsh operating conditions. Tungsten is the leading candidate for the divertor, a -crucial plasma facing component. This dissertation focuses on modeling the behavior of tungsten under irradiation conditions relevant to the divertor operations using a multi-scale modeling -approach. In particular, high fluxes of helium ions at low energy impact the divertor and are responsible for changes in the tungsten microstructure such as the formation of helium blisters and -”fuzz”-like structures which can ultimately lead to erosion, degradation of materials performance -and materials failure. -A spatially dependent cluster dynamics model is introduced in order to model the evolution of -the tungsten microstructure under irradiation. This continuum model is based on kinetic rate theory and handles each material defect type independently. Under the assumptions of a low dilute -limit and no spatial correlation between defects, this leads to a large system of non-linear reactiondiffusion equations. Hence, the results addressed in this thesis consist in the determination of the -kinetic parameters for the cluster dynamics model, the construction of a solver which efficiently -deals with the large non-linear system of partial differential equations, the determination of the -applicability of the model to fusion relevant conditions, and the model results for a variety of irradiation conditions. -The input kinetic parameters to the cluster dynamics model are the defects’ diffusion coefficients, binding energies and capture radii. These can be determined using a molecular dynamics and -density functional theory simulations as well as empirical data. The challenge lies in obtaining a -consistent set of kinetic parameters. Therefore, a method to determine the value of the diffusion -coefficients for small helium, interstitial and vacancy defects at various temperatures using only -molecular dynamics simulations is presented. Binding energies are also determined using molecular dynamics, and when combined with the diffusion coefficients they form a consistent set of -kinetic parameters. -An efficient implementation of a parallel solver is presented to deal with the large number of stiff -non linear reaction diffusion equations. The implementation of a SDIRK scheme using a modified version of the SPIKE algorithm gives excellent parallelization results and suggests that this -implementation would also be efficient for an extension of the model to two or three dimensions. -Convergence results for a variety of SDIRK schemes show a convergence order reduction of the -numerical scheme due to the stiffness of the reaction and diffusion terms. -A comparison between simulation results using the cluster dynamics model and experimental results is essential to assess the validity of the model. Comparison with thermal helium desorption -spectrometry experiments at low flux and fluence shows an excellent agreement between simulation and experiments and indicate that the model captures the key physical properties affecting the -evolution of the tungsten microstructure. Further comparison with molecular dynamics simulations -at extremely high fluxes provides an insight in the expected limitations of the model due to surface effects and dilute limit approximations breakdown when applied to fusion relevant conditions. -Results of the model under fusion relevant conditions show the formation of large helium bubbles under the surface at a temperature dependent depth. The results are very sensitive to both -irradiation flux and temperature. At large temperatures, a small concentration of large bubbles -forms first deep under the tungsten surface, and forms a “plug” which moves towards the surface -until eventually the dilute limit approximation breaks down, indicating that the sub-surfaces bubbles become interlinked. At small temperatures, a larger concentration of smaller bubbles forms -close to the surface until eventually surface effects such as bubble bursting are expected to occur. -These results are found to be in good agreement with a similar analytical reaction diffusion model -for fusion relevant conditions. More work is needed to simulate past the dilute limit breakdown -and examine the possibility of taking into account surface effects.}, - school = {UC Berkeley}, - author = {Faney, Thibault}, - year = {2013}, - file = {Faney_berkeley_0028E_13965.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W242ND3C\\Faney_berkeley_0028E_13965.pdf:application/pdf}, + number = {7}, + urldate = {2021-06-18}, + journal = {Nuclear Fusion}, + author = {Fan, Cuncai and Katoh, Yutai and Hu, Xunxiang}, + month = jun, + year = {2021}, + note = {Publisher: IOP Publishing}, + pages = {076011}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\URV3P6F9\\Fan et al. - 2021 - Impact of helium irradiation on the crystallograph.pdf:application/pdf}, } -@article{fichtl_temperature_2014, - title = {On the {Temperature} {Programmed} {Desorption} of {Hydrogen} from {Polycrystalline} {Copper}}, - volume = {144}, - issn = {1572-879X}, - url = {https://doi.org/10.1007/s10562-014-1384-4}, - doi = {10.1007/s10562-014-1384-4}, - abstract = {Temperature programmed hydrogen desorption (H2-TPD) is a versatile tool to characterize metal surfaces in heterogeneous catalysts. We present a systematic H2-TPD study combined with a kinetic analysis of the H2 desorption process from pure polycrystalline copper and alumina supported copper. The results show that, in contrast to typical Cu/ZnO based methanol synthesis catalysts, the alumina support has no measureable influence on the desorption process and that the copper surface in both catalyst can be accurately described by a theoretically deduced mixture of the low index planes Cu(100), Cu(110), and Cu(111).Graphical Abstract Open image in new window}, +@article{imbeaux_design_2015, + title = {Design and first applications of the {ITER} integrated modelling \& analysis suite}, + volume = {55}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/0029-5515/55/12/123006}, + doi = {10.1088/0029-5515/55/12/123006}, + abstract = {The ITER Integrated Modelling \& Analysis Suite (IMAS) will support both plasma operation and research activities on the ITER tokamak experiment. The IMAS will be accessible to all ITER members as a key tool for the scientific exploitation of ITER. The backbone of the IMAS infrastructure is a standardized, machine-generic data model that represents simulated and experimental data with identical structures. The other outcomes of the IMAS design and prototyping phase are a set of tools to access data and design integrated modelling workflows, as well as first plasma simulators workflows and components implemented with various degrees of modularity.}, language = {en}, number = {12}, - urldate = {2019-11-22}, - journal = {Catalysis Letters}, - author = {Fichtl, Matthias B. and Hinrichsen, Olaf}, - month = dec, - year = {2014}, - keywords = {Experiment, Catalysis, Copper, Copper catalysts, Elementary kinetics, Heterogeneous catalysis}, - pages = {2114--2120}, - file = {Fichtl et Hinrichsen - 2014 - On the Temperature Programmed Desorption of Hydrog.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3LIA6BLI\\Fichtl et Hinrichsen - 2014 - On the Temperature Programmed Desorption of Hydrog.pdf:application/pdf}, + urldate = {2021-06-17}, + journal = {Nuclear Fusion}, + author = {Imbeaux, F. and Pinches, S. D. and Lister, J. B. and Buravand, Y. and Casper, T. and Duval, B. and Guillerminet, B. and Hosokawa, M. and Houlberg, W. and Huynh, P. and Kim, S. H. and Manduchi, G. and Owsiak, M. and Palak, B. and Plociennik, M. and Rouault, G. and Sauter, O. and Strand, P.}, + month = oct, + year = {2015}, + note = {Publisher: IOP Publishing}, + pages = {123006}, + file = {Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\3D6BYZUC\\Imbeaux et al. - 2015 - Design and first applications of the ITER integrat.pdf:application/pdf}, } -@article{mudiyanselage_adsorption_2013, - title = {Adsorption of hydrogen on the surface and sub-surface of {Cu}(111)}, - volume = {139}, - issn = {0021-9606, 1089-7690}, - url = {http://aip.scitation.org/doi/10.1063/1.4816515}, - doi = {10.1063/1.4816515}, +@article{schmid_use_2021, + title = {On the use of recombination rate coefficients in hydrogen transport calculations}, + issn = {0029-5515}, + url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac07b2}, + doi = {10.1088/1741-4326/ac07b2}, + abstract = {The commonly accepted picture for the uptake of hydrogen isotopes (HIs) from the gas phase across the surface into a metal with an endothermic heat of solution for HIs is that of dissociation followed by thermalisation in a chemisorbed surface state and finally overcoming a surface barrier to enter the metal bulk where the HIs occupy interstitial solute sites. To leave the metal bulk the HIs first transition to the chemisorbed surface state from which they then enter gas phase by recombining into a diatomic molecule. This model is generally attributed to the work of Pick and Sonnenberg from 1985. They clearly distinguish surface states and subsurface solute sites where the recombination flux is proportional to the square of the concentration of chemisorbed atoms due the diatomic nature of this Langmuir–Hinshelwood process. In an effort to compare their extended model with an earlier surface model by Waelbroeck, which uses an expression for the recombination flux proportional to the square of the sub-surface interstitial solute concentration, they derive an effective recombination coefficient. However, also with the so-derived Pick and Sonnenberg recombination coefficient, the Waelbroeck model is only applicable under certain conditions. But, due to its simplicity, it is often used in boundary conditions of diffusion trapping type calculations, generally ignoring whether or not these conditions are met. This paper will use the full Pick and Sonnenberg model implemented in the TESSIM-X code and in simplified algebraic approximations, to show the limits of applicability of the Waelbroeck-Ansatz in modelling hydrogen transport in metals foreseen for the first wall of magnetic confinement fusion devices.}, language = {en}, - number = {4}, - urldate = {2019-11-22}, - journal = {The Journal of Chemical Physics}, - author = {Mudiyanselage, Kumudu and Yang, Yixiong and Hoffmann, Friedrich M. and Furlong, Octavio J. and Hrbek, Jan and White, Michael G. and Liu, Ping and Stacchiola, Darío J.}, - month = jul, - year = {2013}, - keywords = {Experiment, Copper}, - pages = {044712}, - file = {Mudiyanselage et al. - 2013 - Adsorption of hydrogen on the surface and sub-surf.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BAGPXHNW\\Mudiyanselage et al. - 2013 - Adsorption of hydrogen on the surface and sub-surf.pdf:application/pdf}, + urldate = {2021-06-15}, + journal = {Nuclear Fusion}, + author = {Schmid, Klaus and Zibrov, Mikhail}, + year = {2021}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\B34HU4YR\\Schmid et Zibrov - 2021 - On the use of recombination rate coefficients in h.pdf:application/pdf}, } -@article{cao_hydrogen_2018, - title = {Hydrogen adsorption and desorption from {Cu}(111) and {Cu}(211)}, - volume = {20}, - issn = {1463-9084}, - url = {https://pubs.rsc.org/en/content/articlelanding/2018/cp/c8cp03386b}, - doi = {10.1039/C8CP03386B}, - abstract = {We present a combined experimental–theoretical study on structural and coverage dependences of the adsorption and desorption of molecular hydrogen on atomically flat Cu(111) and highly stepped Cu(211) surfaces. For molecules with identical incident energy from supersonic molecular beams, we find a reduced dissociative sticking probability for the stepped surface compared to Cu(111). DFT calculations of activation barriers to dissociation for the clean and partially precovered surfaces, as well as quantitative analysis of TPD spectra, support that the A-type step of the (211) surface causes an upward shift in activation barriers to dissociation and lowering of the desorption barrier. The new data allow us to determine low sticking probabilities at conditions where King and Wells measurements fail to determine the reactivity. They are also fully consistent with the unexpected observation that monoatomic steps on a surface lower the reactivity toward the dissociation of a diatomic molecule.}, - language = {en}, - number = {35}, - urldate = {2019-11-22}, - journal = {Physical Chemistry Chemical Physics}, - author = {Cao, Kun and Füchsel, Gernot and Kleyn, Aart W. and Juurlink, Ludo B. F.}, - month = sep, - year = {2018}, - keywords = {Experiment, Copper}, - pages = {22477--22488}, - file = {Cao et al. - 2018 - Hydrogen adsorption and desorption from Cu(111) an.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8LEAR3YL\\Cao et al. - 2018 - Hydrogen adsorption and desorption from Cu(111) an.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BUB7QRYW\\c8cp03386b.html:text/html}, +@article{shimada_overview_2012, + series = {Tenth {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-10)}, + title = {Overview of the {US}–{Japan} collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten}, + volume = {87}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379612001779}, + doi = {10.1016/j.fusengdes.2012.02.103}, + abstract = {The effect of neutron-irradiation damage has been mainly simulated using high-energy ion bombardment. A recent MIT report (PSFC/RR-10-4, An assessment of the current data affecting tritium retention and its use to project towards T retention in ITER, Lipschultz et al., 2010) summarizes the observations from high-energy ion bombardment studies and illustrates the saturation trend in deuterium concentration due to damage from ion irradiation in tungsten and molybdenum above 1 displacement per atom (dpa). While this prior database of results is quite valuable for understanding the behavior of hydrogen isotopes in plasma facing components (PFCs), it does not encompass the full range of effects that must be considered in a practical fusion environment due to short penetration depth, damage gradient, high damage rate, and high primary knock-on atom (PKA) energy spectrum of the ion bombardment. In addition, neutrons change the elemental composition via transmutations, and create a high radiation environment inside PFCs, which influences the behavior of hydrogen isotope in PFCs, suggesting the utilization of fission reactors is necessary for neutron-irradiation. Under the framework of the US–Japan TITAN program, tungsten samples (99.99at.\% purity from A.L.M.T. Co.) were irradiated by fission neutrons in the High Flux Isotope Reactor (HFIR), Oak Ridge National Laboratory (ORNL), at 50 and 300°C to 0.025, 0.3, and 2.4dpa, and the investigation of deuterium retention in neutron-irradiated tungsten was performed in the Tritium Plasma Experiment (TPE), the unique high-flux linear plasma facility that can handle tritium, beryllium and activated materials. This paper reports the recent results from the comparison of ion-damaged tungsten via various ion species (2.8MeV Fe2+, 20MeV W2+, and 700keV H−) with that from neutron-irradiated tungsten to identify the similarities and differences among them.}, + language = {en}, + number = {7}, + urldate = {2021-06-09}, + journal = {Fusion Engineering and Design}, + author = {Shimada, Masashi and Hatano, Y. and Oya, Y. and Oda, T. and Hara, M. and Cao, G. and Kobayashi, M. and Sokolov, M. and Watanabe, H. and Tyburska-Püschel, B. and Ueda, Y. and Calderoni, P. and Okuno, K.}, + month = aug, + year = {2012}, + keywords = {Tungsten, Neutron-irradiation, Tritium retention, Ion-damage, Linear plasma device, Neutron}, + pages = {1166--1170}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\B3BQPLD8\\Shimada et al. - 2012 - Overview of the US–Japan collaborative investigati.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2BVG2R8N\\S0920379612001779.html:text/html}, } -@article{amador_effect_2019, - title = {The {Effect} of {Pulsed} {Current} and {Organic} {Additives} on {Hydrogen} {Incorporation} in {Electroformed} {Copper} {Used} in {Ultrahigh} {Vacuum} {Applications}}, - volume = {166}, - issn = {0013-4651, 1945-7111}, - url = {http://jes.ecsdl.org/content/166/10/D366}, - doi = {10.1149/2.1211908jes}, - abstract = {The presence of hydrogen in electroformed copper from two different acidic copper sulfate solutions was evaluated: an additive-free solution and a solution including a sugar. D-xylose addition is found to inhibit H incorporation and allows the use of higher cathodic pulses before the copper diffusion limited range starts. TDS experiments show that hydrogen is trapped in the copper samples in two different forms. Hydrogen diffused from copper vacancies was found on all samples at an outgassing temperature of around 450°C. For samples with long pulse times, an additional H2 outgassing peak was found at around 600°C. XRD measurements allowed us to determine the preferential orientation of the plated samples and to monitor lattice parameter evolution with increasing temperature.}, +@article{meschini_arc_2021, + title = {{ARC} reactor: {A} preliminary tritium environmental impact study}, + volume = {167}, + issn = {0920-3796}, + shorttitle = {{ARC} reactor}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621001162}, + doi = {10.1016/j.fusengdes.2021.112340}, + abstract = {The fusion pilot power plant ARC is a conceptual design of a D–T Tokamak under investigation at the Massachusetts Institute of Technology. Special attention is paid on the radiological hazard, which until now has been translated in the reduction of materials activation. Indeed, one of ARC main goals is to be fast deployable in any US site: thus, the radiological risk associated to its presence must be minimized, both for the population and the environment. Tritium is one of the main sources of radiological hazard in ARC and it is almost ubiquitous: it is found in the vacuum chamber, in the blanket, in structural materials and in tritium processing and storing components. In this work, a safety analysis is proposed to quantify the radioactivity release following an accidental scenario. Tritium inventories in the main components are estimated starting from the preliminary design of the FLiBe circuit. The source term is quantified assuming the occurrence of a severe accident damaging key components. Afterward, the environmental impact and the doses to the most exposed individuals are evaluated through suitable population doses codes, and ARC compliance with safety limits is assessed.}, language = {en}, - number = {10}, - urldate = {2019-11-22}, - journal = {Journal of The Electrochemical Society}, - author = {Amador, L. Lain and Rolet, J. and Doche, M.-L. and Massuti-Ballester, P. and Gigandet, M.-P. and Moutarlier, V. and Taborelli, M. and Ferreira, L. M. A. and Chiggiato, P. and Hihn, J.-Y.}, - month = jan, - year = {2019}, - keywords = {Experiment, Copper}, - pages = {D366--D373}, - file = {Amador et al. - 2019 - The Effect of Pulsed Current and Organic Additives.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4ALGFT57\\Amador et al. - 2019 - The Effect of Pulsed Current and Organic Additives.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KWEGE895\\D366.html:text/html}, + urldate = {2021-06-04}, + journal = {Fusion Engineering and Design}, + author = {Meschini, Samuele and Testoni, Raffaella and Segantin, Stefano and Zucchetti, Massimo}, + month = jun, + year = {2021}, + keywords = {Tritium, Safety, Tokamak, ARC reactor, Radiological release}, + pages = {112340}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2ZRJAF74\\Meschini et al. - 2021 - ARC reactor A preliminary tritium environmental i.pdf:application/pdf}, } -@article{anderl_hydrogen_1990, - title = {Hydrogen transport behavior of metal coatings for plasma-facing components}, - volume = {176-177}, +@article{lee_temperature-dependent_2021, + title = {Temperature-{Dependent} {Model} of {Helium} {Bubble} {Expansion} and {Bursting} in {Tungsten}}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/0022311590901279}, - doi = {10.1016/0022-3115(90)90127-9}, - abstract = {Plasma-facing components for experimental and commercial fusion reactor studies may include cladding or coatings of refractory metals like tungsten on metallic structural substrates such as copper, vanadium alloys and austenitic stainless steel. Issues of safety and fuel economy include the potential for inventory buildup and permeation of tritium implanted into the plasma-facing surface. This paper reports on laboratory-scale studies with 3 keV D+3 ion beams to investigate the hydrogen transport behavior in tungsten coatings on substrates of copper. These experiments entailed measurements of the deuterium re-emission and permeation rates for tungsten, copper, and tungsten-coated copper specimens at temperatures ranging from 638 to 825 K and implanting particle fluxes of approximately 5 × 1019 D/m2 s. Diffusion constants and surface recombination coefficients with enhancement factors due to sputtering were obtained from these measurements. These data may be used in calculations to estimate permeation rates and inventory buildups for proposed diverter designs.}, + url = {https://www.sciencedirect.com/science/article/pii/S002231152100324X}, + doi = {10.1016/j.jnucmat.2021.153101}, + abstract = {Continuum-scale models that can reliably predict the behavior of helium in tungsten are of interest to the fusion community due to the projected impact of these materials on fusion reactor operation. We perform molecular dynamics simulations of spherical helium bubbles of various sizes in tungsten at different temperatures and depths with the goal of determining a mathematical model of the pressure and density at which the bubbles initially expand or burst as a function of depth, size, temperature, and surface orientation. The bubbles are small enough that their loop-punching pressures cannot be accurately predicted with continuum mechanics, and their expansion behavior is important, as it appears to cause many of the features observed on helium-irradiated tungsten surfaces. We vary the temperature, bubble size, bubble depth, and surface orientation in each case, recording the bubble pressure and density that result in bubble expansion. An exponential function with three adjustable parameters is found to fit the results well; the parameters that best fit our results are provided.}, language = {en}, - urldate = {2019-11-22}, + urldate = {2021-06-02}, journal = {Journal of Nuclear Materials}, - author = {Anderl, R. A. and Holland, D. F. and Longhurst, G. R.}, - month = dec, - year = {1990}, - keywords = {Experiment, Copper}, - pages = {683--689}, - file = {Anderl et al. - 1990 - Hydrogen transport behavior of metal coatings for .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9N46YH75\\Anderl et al. - 1990 - Hydrogen transport behavior of metal coatings for .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A94XN6LD\\0022311590901279.html:text/html}, -} - -@article{wilson_hydrogen_1987, - title = {Hydrogen isotope retention and release from copper}, - volume = {5}, - issn = {0734-2101}, - url = {https://avs.scitation.org/doi/10.1116/1.574444}, - doi = {10.1116/1.574444}, - number = {4}, - urldate = {2019-11-22}, - journal = {Journal of Vacuum Science \& Technology A}, - author = {Wilson, K. L. and Causey, R. A. and Baskes, M. I. and Kamperschroer, J.}, - month = jul, - year = {1987}, - keywords = {Experiment, Copper}, - pages = {2319--2324}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PSWXRMKX\\1.html:text/html}, + author = {Lee, Brandon F. and Hammond, Karl D.}, + month = may, + year = {2021}, + keywords = {Tungsten, Helium, Bubble, Plasma-facing}, + pages = {153101}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4VLTBG2B\\S002231152100324X.html:text/html}, } -@article{penalva_interaction_2012, - title = {Interaction of {Copper} {Alloys} with {Hydrogen}}, - url = {https://www.intechopen.com/books/copper-alloys-early-applications-and-current-performance-enhancing-processes/interaction-of-copper-alloys-with-hydrogen}, - doi = {10.5772/34469}, - abstract = {Open access peer-reviewed chapter}, - language = {en}, - urldate = {2019-10-07}, - journal = {Copper Alloys - Early Applications and Current Performance - Enhancing Processes}, - author = {Peñalva, I. and Alberro, G. and Legarda, F. and Esteban, G. A. and Riccardi, B.}, - month = mar, - year = {2012}, - keywords = {Experiment, Copper}, - file = {Peñalva et al. - 2012 - Interaction of Copper Alloys with Hydrogen.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\585MS3D4\\Peñalva et al. - 2012 - Interaction of Copper Alloys with Hydrogen.pdf:application/pdf}, +@article{schmidt_effects_2021, + title = {Effects of {Radiation}-{Induced} {Defects} on {Corrosion}}, + volume = {51}, + url = {https://doi.org/10.1146/annurev-matsci-080819-123403}, + doi = {10.1146/annurev-matsci-080819-123403}, + abstract = {The next generation of nuclear reactors will expose materials to conditions that, in some cases, are even more extreme than those in current fission reactors, inevitably leading to new materials science challenges. Radiation-induced damage and corrosion are two key phenomena that must be understood both independently and synergistically, but their interactions are often convoluted. In the light water reactor community, a tremendous amount of work has been done to illuminate irradiation-corrosion effects, and similar efforts are under way for heavy liquid metal and molten salt environments. While certain effects, such as radiolysis and irradiation-assisted stress corrosion cracking, are reasonably well established, the basic science of how irradiation-induced defects in the base material and the corrosion layer influence the corrosion process still presents many unanswered questions. In this review, we summarize the work that has been done to understand these coupled extremes, highlight the complex nature of this problem, and identify key knowledge gaps. Expected final online publication date for the Annual Review of Materials Science, Volume 51 is August 2021. Please see http://www.annualreviews.org/page/journal/pubdates for revised estimates.}, + number = {1}, + urldate = {2021-06-01}, + journal = {Annual Review of Materials Research}, + author = {Schmidt, Franziska and Hosemann, Peter and Scarlat, Raluca O. and Schreiber, Daniel K. and Scully, John R. and Uberuaga, Blas P.}, + year = {2021}, + note = {\_eprint: https://doi.org/10.1146/annurev-matsci-080819-123403}, + pages = {null}, } -@article{lloyd_surface_1997, - title = {Surface and bulk interactions of hydrogen with copper}, - volume = {119}, - issn = {01694332}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0169433297001797}, - doi = {10.1016/S0169-4332(97)00179-7}, - abstract = {The permeation of deuterium through a 25 /{\textasciitilde}m Cu foil was investigated using an atomic deuterium source. The diffusivity of deuterium in Cu at temperatures from 350-550 K was measured. Diffusivities observed in this study are in good agreement with reported values observed at higher temperatures (circa 800-1000 K). Use of an atomic deuterium source provided high internal pressures and superinventory effects analogous to those reported for various hydrogen-metal systems. Data collected in this study together with thermal desorption studies have been used to develop a comprehensive Lennard-Jones potential model for the Cu/D system. © 1997 Elsevier Science B.V.}, - language = {en}, - number = {3-4}, - urldate = {2019-11-22}, - journal = {Applied Surface Science}, - author = {Lloyd, Peter B. and Kress, John W. and Tatarchuk, Bruce J.}, - month = oct, - year = {1997}, - keywords = {Experiment, Copper}, - pages = {275--287}, - file = {Lloyd et al. - 1997 - Surface and bulk interactions of hydrogen with cop.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U8TGZYZH\\Lloyd et al. - 1997 - Surface and bulk interactions of hydrogen with cop.pdf:application/pdf}, +@misc{noauthor_integration_nodate, + title = {Integration issues on tritium management of the {European} {DEMO} {Breeding} {Blanket} and ancillary systems - {ScienceDirect}}, + url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/science/article/pii/S0920379621003495?via%3Dihub}, + urldate = {2021-05-28}, + file = {Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\G3JAVNZ5\\S0920379621003495.html:text/html}, } -@article{perkins_permeation_1972, - title = {Permeation and diffusion of hydrogen in ceramvar, copper, and ceramvar-copper laminates}, - volume = {76}, - copyright = {Copyright © 1972 Wiley‐VCH Verlag GmbH \& Co. KGaA, Weinheim}, - issn = {0005-9021}, - url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/bbpc.19720760866}, - doi = {10.1002/bbpc.19720760866}, +@article{markelj_deuterium_2020, + title = {Deuterium transport and retention in the bulk of tungsten containing helium: the effect of helium concentration and microstructure}, + volume = {60}, + issn = {0029-5515}, + shorttitle = {Deuterium transport and retention in the bulk of tungsten containing helium}, + url = {https://doi.org/10.1088/1741-4326/abadae}, + doi = {10.1088/1741-4326/abadae}, + abstract = {The effect of helium (He) on deuterium (D) retention and transport in the bulk of tungsten (W) was investigated. For this purpose samples were irradiated by 500 keV He ions at 300 K to different fluences in order to obtain He maximum concentrations of 1 at.\%, 3.4 at.\%, and 6.8 at.\% in 0.84 µm depth. In order to discern the effect of irradiation damage caused by He implantation from the effect of the pure He presence on D retention, the W samples were irradiated at 300 K by 20 MeV W ions in advance to create displacement damage in the crystal lattice to a damage dose of 0.23 dpa. The samples were exposed to a D atom beam at 600 K with a flux of 3.5 × 1018 D m−2s−1 to populate all the created defects. The D depth profiles were measured in situ during and at the end of exposure by nuclear reaction analysis to follow the dynamics of the D uptake. Thermal desorption spectra were collected ex situ at the end of the exposure. We show that D retention increases with implanted He fluence linearly following a D/He ratio of 0.29. We obtained peaking of D concentration at the position of maximum He concentration, reaching for the 6.8 at.\% He sample three times higher D concentration (1.1 at.\%) than obtained on high dpa W ion irradiated samples (0.37 at.\%) for the same loading conditions. D retention and transport was also studied on He-containing samples that were annealed to 1700 K. There was no reduction of D retention in the He zone but 80\% reduction in the only W irradiated zone was observed, meaning displacement damage was almost completely removed. In the He zone the D concentration increased to 1.35 at.\%, and we attribute this to trapping of D around He bubbles of 1.5 nm size created at the He peak maximum as obtained by transmission electron microscopy. Neither in the as He implanted nor the 1700 K annealed sample did He act as diffusion barrier. From this study we can conclude that in the main wall of a future fusion device the effect of He will not dominate D retention in W, but at high heat flux areas where displacement damage possibly anneals out He could accumulate in the material and it could eventually dominate over the effect of displacement damage.}, language = {en}, - number = {8}, - urldate = {2019-11-22}, - journal = {Berichte der Bunsengesellschaft für physikalische Chemie}, - author = {Perkins, W. G. and Begeal, D. R.}, - year = {1972}, - keywords = {Experiment, Copper}, - pages = {863--863}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VGVPLNVQ\\bbpc.html:text/html}, + number = {10}, + urldate = {2021-05-27}, + journal = {Nuclear Fusion}, + author = {Markelj, S. and Schwarz-Selinger, T. and Pečovnik, M. and Chrominski, W. and Šestan, A. and Zavašnik, J.}, + month = sep, + year = {2020}, + note = {Publisher: IOP Publishing}, + pages = {106029}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SJKD8JMA\\Markelj et al. - 2020 - Deuterium transport and retention in the bulk of t.pdf:application/pdf}, } -@article{magnusson_self-diffusion_2013, - title = {Self-diffusion and impurity diffusion of hydrogen, oxygen, sulphur and phosphorus in copper}, - abstract = {A study on the mobility of hydrogen, oxygen, sulphur, and phosphorus in copper has been made. -In addition, the self-diffusion of copper has also been studied. Literature data has been reviewed, -and used to evaluate the temperature expressions of the diffusion coefficients of these elements in -copper. The interstitial elements oxygen and hydrogen have been described by a single temperature -expression in the whole temperature range, whereas the substitutional elements copper, sulphur, -and phosphorus have been modelled according to lattice diffusion at high temperatures and grain -boundary diffusion at low temperatures. -Sulphur, phosphorus, and copper are believed to be nearly immobile within the crystalline grains -at low temperature, even for time periods up to 100,000 years. On the other hand, in the grain -boundaries these elements can diffuse and an upper limit estimate of the possible diffusion distance -has been made. At room temperature sulphur can diffuse up to 5 cm for 100,000 years, whereas both -phosphorus and copper requires more than 1,000 000 years to diffuse the same distance. The oxygen -atom shows a similar mobility, although it is interstitially diffusing through the grains. However, -since both oxygen and sulphur have a very low solubility any measureable mass transport of these -elements will never take place at low temperatures. They will instead form oxides and sulphides in -the material. -Hydrogen is a mobile element, and will be able to diffuse through 5 cm of copper during a time period -of 1,000 years at room temperature. The diffusion of hydrogen in copper is experimentally well studied -down to room temperature. By combining the evaluated hydrogen diffusion coefficient with the -thermodynamically calculated hydrogen content in solid solution the permeability of hydrogen can be -explained. This can be used to explain the mass-transport of hydrogen for different times, temperatures, -and hydrogen activities (pressures).}, +@article{baldwin_influence_2021, + title = {The influence of {D2} pressure on {D} retention and release from {Be} co-deposits}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S235217912100096X}, + doi = {10.1016/j.nme.2021.101023}, + abstract = {Beryllium co-deposit thermal desorption studies are reported that focus on the effect of D2 pressure during layer formation, as pressure has been linked in prior work to the formation of a high-retention-capacity sharp-release-feature. A pressure range from 0.3 to 13.3 Pa is explored. Additional insight into what drives the formation of T0 is established through co-deposit formation parameter variations including deposition temperature spanning 373 K to 608 K, and ion impact energy in the range 10-100 eV. It is found that the formation of the sharp release feature exhibits a multi-parameter dependence, but is predominately favored by low deposition temperature, higher D2 pressure, and to a small degree, increased ion impact energy, during deposition. TESSIM simulations of the D2 thermal release at the ITER bake temperatures of Tb1 (513 K) and Tb2 (623 K), show that the best efficacy for D removal (defined as the ratio of post to pre bake inventory) is found when the sharp release feature is present. However, when this feature is present, the total retained D inventory tends to be significantly increased.}, language = {en}, - author = {Magnusson, Hans and Frisk, Karin}, - month = dec, - year = {2013}, - keywords = {Experiment, Copper}, - pages = {33}, - file = {Magnusson et Frisk - Self-diffusion and impurity diffusion of hydrogen,.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4NKYXHFM\\Magnusson et Frisk - Self-diffusion and impurity diffusion of hydrogen,.pdf:application/pdf}, -} - -@article{sakamoto_electrochemical_1982, - title = {The {Electrochemical} {Determination} of {Diffusivity} and {Solubility} of {Hydrogen} in {Copper}}, - volume = {46}, - doi = {10.2320/jinstmet1952.46.3_285}, - abstract = {The diffusivity and solubility of hydrogen in both annealed and as-cold-rolled copper were determined at room temperature by means of the electrochemical permeation method under the galvanostatic charging condition. Results obtained were as follows:(1) The observed build-up transient of hydrogen permeation through Cu foil specimens coincided with the theoretical transient which is the boundary condition of constant hydrogen concentration directly beneath the cathodic surface. Furthermore, the specimen thickness dependence of the steady state permeation current density was examined and consequently, the diffusion of hydrogen through the Cu foil in the permeation process was the rate determining step.(2) The diffusivity in the annealed Cu did not depend on the cathodic current densities in the range of ic=2.5 to 250 A·m−2, i.e., the hydrogen concentration in the cathodic surface, but in the case of as-cold-rolled Cu, it was slightly low, when the hydrogen was introduced at low ic values. While the solubility of hydrogen beneath the cathodic surface for each specimen increased with an increase of ic value, the difference of solubility between the annealed Cu specimen and the as-cold-rolled one was not remarkable at 315±1 K.(3) The temperature dependences of the diffusivity (D) and solubility (C) of hydrogen in the annealed Cu determined at the temperature range of 292 to 339 K under ic=10 A·m−2 can be described as follows:(This article is not displayable. Please see full text pdf.) {\textbackslash} -oindentOn the other hand, compared with annealed Cu, the as-cold-rolled Cu had a lower diffusivity and slightly higher activation energy for diffusion, and the hydrogen absorption occurred by the exothermic reaction.}, - number = {3}, - journal = {Journal of the Japan Institute of Metals}, - author = {Sakamoto, Yoshiichi and Takao, Keizo}, - year = {1982}, - keywords = {Copper, Experiment}, - pages = {285--290}, - file = {Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7YM46RCF\\Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:application/pdf;J-Stage - Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CCJFTBT6\\en.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QG77JNDI\\Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:application/pdf}, + urldate = {2021-05-27}, + journal = {Nuclear Materials and Energy}, + author = {Baldwin, M. J. and Založnik, A. and Simmonds, M. J. and Temmerman, G. De and Doerner, R. P.}, + month = may, + year = {2021}, + keywords = {Retention, Beryllium, Co-deposits, Thermal desorption}, + pages = {101023}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\W83E6UEJ\\S235217912100096X.html:text/html}, } -@article{ishikawa_diffusivity_1985, - title = {The diffusivity of hydrogen in copper at low temperatures}, - volume = {46}, - issn = {00223697}, - url = {https://linkinghub.elsevier.com/retrieve/pii/0022369785901106}, - doi = {10.1016/0022-3697(85)90110-6}, - abstract = {An electrochemical method has been used to measure the diffusivity of hydrogen in copper in the temperature range 299-322.5 K. Both uncoated and Pd-coated copper foils were used. The measurements show, in combination with other data, that there are no deviations from classical Arrhenius diffusion behavior in the entire temperature range from 1200 down to 300 K.}, +@article{liu_major_2020, + title = {The major trap sites of deuterium in {CuCrZr} alloy}, + volume = {23}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179120300314}, + doi = {10.1016/j.nme.2020.100755}, + abstract = {The energy characteristics of the main deuterium (D) traps in CuCrZr alloy samples, which were previously annealed at temperatures of 773, 873, 973 and 1073 K and then exposed to D2 gas at a pressure of 2.5 × 104 Pa and a temperature of 723 K for 10 h, were studied by thermal desorption spectroscopy. Samples of oxygen free copper (OFC) were also investigated in the same way. For OFC, annealing at 773 K could reduce D retention appreciably. It indicates the temperature of 773 K is high enough to reduce the total D amount trapped by intrinsic defects (i.e. vacancies, dislocations and grain boundaries). However, for CuCrZr alloy, heat treatment does not reduce the D retention significantly until the annealing temperature is higher than 1073 K. Scanning electron microscope (SEM) and energy dispersive spectrometer (EDS) observations show that the density of precipitate particles especially the Zr-rich precipitate particles increase for the 1073 K-annealed one. It suggests the dissolved Zr atoms in the substrate are responsible for the D retention in CuCrZr alloy. D detrapping energy from the dissolved Zr atoms in CuCrZr alloy is estimated to be 0.98 eV from the TDS measurements.}, language = {en}, - number = {4}, - urldate = {2019-11-22}, - journal = {Journal of Physics and Chemistry of Solids}, - author = {Ishikawa, Thomaz and McLellan, Rex B.}, - month = jan, - year = {1985}, - keywords = {Experiment, Copper}, - pages = {445--447}, - file = {Ishikawa et McLellan - 1985 - The diffusivity of hydrogen in copper at low tempe.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GAHNP7UP\\Ishikawa et McLellan - 1985 - The diffusivity of hydrogen in copper at low tempe.pdf:application/pdf}, + urldate = {2021-05-26}, + journal = {Nuclear Materials and Energy}, + author = {Liu, Hao-Dong and Zhou, Hai-Shan and Zhao, Si-Xiang and Wang, Lu and Wei, Ran and Luo, Guang-Nan}, + month = may, + year = {2020}, + keywords = {Retention, Hydrogen isotope, CuCrZr alloy, Heat treatment}, + pages = {100755}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Z9XWYPEE\\Liu et al. - 2020 - The major trap sites of deuterium in CuCrZr alloy.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QUI9ESPI\\S2352179120300314.html:text/html}, } -@article{nagai_hydrogen_1996, - title = {Hydrogen desorption from copper during ion bombardment measured by {SIMS}}, - volume = {47}, - issn = {0042207X}, - url = {https://linkinghub.elsevier.com/retrieve/pii/0042207X96001479}, - doi = {10.1016/0042-207X(96)00147-9}, - abstract = {Secondary ion mass spectrometry (SIMS) is a sensitive analysis method for hydrogen. In this paper, SIMS is used to observe the hydrogen desorption from copper caused by an ion bombardment, and the measurements reveal the following: hydrogen ion intensity is reduced by the industrial manufacturing procedure of copper, i.e. intermediate annealing and cold working. The less porosities the copper includes, the less hydrogen desorption it shows even though the hydrogen concentration of copper bulk is the same. The former suggests that hydrogen desorption from copper is promoted by thermal diffusion and grain boundary diffusion, and the latter suggests that the hydrogen desorption phenomena is closely related to the microstructural defects like grain boundaries or porosities that enhance the diffusion of hydrogen. Copyright 0 1996 Elsevier Science Ltd.}, - language = {en}, - number = {6-8}, - urldate = {2019-11-22}, - journal = {Vacuum}, - author = {Nagai, Y and Saito, Y and Matuda, N}, - month = jun, - year = {1996}, - keywords = {Experiment, Copper}, - pages = {737--739}, - file = {Nagai et al. - 1996 - Hydrogen desorption from copper during ion bombard.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NT4759FQ\\Nagai et al. - 1996 - Hydrogen desorption from copper during ion bombard.pdf:application/pdf}, +@article{kreter_linear_2015, + title = {Linear {Plasma} {Device} {PSI}-2 for {Plasma}-{Material} {Interaction} {Studies}}, + volume = {68}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST14-906}, + doi = {10.13182/FST14-906}, + abstract = {The linear plasma device PSI-2 serves as a pilot experiment for the development of components, operational regimes and control systems for the linear plasma device JULE-PSI, which will be located in the nuclear environment allowing studies of radioactive and toxic samples. PSI-2 is also used for fusion reactor relevant plasma-material interaction studies. This contribution describes the PSI-2 layout and parameters and summarizes the recent scientific and technical progress in the project, including the installation of a target station for the sample manipulation and analyses.}, + number = {1}, + urldate = {2021-05-19}, + journal = {Fusion Science and Technology}, + author = {Kreter, A. and Brandt, C. and Huber, A. and Kraus, S. and MÖller, S. and Reinhart, M. and Schweer, B. and Sergienko, G. and Unterberg, B.}, + month = jul, + year = {2015}, + note = {Publisher: Taylor \& Francis +\_eprint: https://doi.org/10.13182/FST14-906}, + pages = {8--14}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QYPFSLTM\\FST14-906.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\D3Q2RAZV\\Kreter et al. - 2015 - Linear Plasma Device PSI-2 for Plasma-Material Int.pdf:application/pdf}, } -@article{elliott_absorption_1995, - title = {Absorption of hydrogen in copper}, - volume = {91}, - issn = {1364-5455}, - url = {https://pubs.rsc.org/en/content/articlelanding/1995/ft/ft9959103659}, - doi = {10.1039/FT9959103659}, - abstract = {Reduction of an alumina-supported copper catalyst under the conditions used as standard for the reduction of the Cu/ZnO/Al2O3 methanol-synthesis catalysts produces multilayers of hydrogen in the copper. This absorption of the hydrogen results in a reconstruction of the copper with the effect that only the surface hydrogen may be thermally desorbed. Thermal desorption of the surface hydrogen allows the surface copper atoms to migrate to a new structure, possibly their original structure, which prohibits thermally induced evolution of the subsurface hydrogen. Reduction of surface oxidised copper containing subsurface hydrogen by CO (0.1 bar, 473 K) results in the explosive evolution of subsurface hydrogen.}, +@article{xie_new_2017, + title = {A new loop-punching mechanism for helium bubble growth in tungsten}, + volume = {141}, + issn = {1359-6454}, + url = {https://www.sciencedirect.com/science/article/pii/S1359645417307395}, + doi = {10.1016/j.actamat.2017.09.005}, + abstract = {Growth of helium (He) bubbles with different initial sizes in tungsten (W) has been investigated by performing molecular dynamics simulations. Based on the simulation results a new loop punching mechanism for the large helium bubble growth is proposed. Different from the growth of small-size He bubbles by pushing out self-interstitial atoms and then rearranging into a prismatic dislocation loop, a large-size bubble grows by pushing out a dislocation, subsequently cross-slipping of its screw components and finally evolving into a prismatic dislocation loop. Such dislocations may react with each other to form a dislocation net around the bubble rather than to convert to prismatic dislocation loops.}, language = {en}, - number = {20}, - urldate = {2019-11-21}, - journal = {Journal of the Chemical Society, Faraday Transactions}, - author = {Elliott, A. J. and Sakakini, B. and Tabatabaei, J. and Waugh, K. C. and Zemicael, F. W. and Hadden, R. A.}, - month = jan, - year = {1995}, - keywords = {Copper}, - pages = {3659--3662}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ICR9VILL\\ft9959103659.html:text/html;Elliott et al. - 1995 - Absorption of hydrogen in copper.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QXCFFQKB\\Elliott et al. - 1995 - Absorption of hydrogen in copper.pdf:application/pdf}, + urldate = {2021-04-03}, + journal = {Acta Materialia}, + author = {Xie, Hongxian and Gao, Ning and Xu, Ke and Lu, Guang-Hong and Yu, Tao and Yin, Fuxing}, + month = dec, + year = {2017}, + keywords = {He bubble growth}, + pages = {10--17}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ZPM9PHAM\\Xie et al. - 2017 - A new loop-punching mechanism for helium bubble gr.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XTJN2RDR\\S1359645417307395.html:text/html}, } -@article{yasumori_mechanism_1974, - title = {Mechanism of {Hydrogen} {Adsorption} and {Hydrogen}-{Deuterium} {Equilibration} on {Copper} {Surface}}, - volume = {13}, - issn = {1347-4065}, - url = {https://iopscience.iop.org/article/10.7567/JJAPS.2S2.485/meta}, - doi = {10.7567/JJAPS.2S2.485}, - language = {en}, - number = {S2}, - urldate = {2019-11-21}, - journal = {Japanese Journal of Applied Physics}, - author = {Yasumori, Iwao and Momma, Naohiro and Kiyomiya, Makoto}, - month = jan, - year = {1974}, - keywords = {Copper}, - pages = {485}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8KTWBQP8\\JJAPS.2S2.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W6APLSH6\\Yasumori et al. - 1974 - Mechanism of Hydrogen Adsorption and Hydrogen-Deut.pdf:application/pdf}, +@article{weerasinghe_non-dilute_2020, + title = {Non-dilute helium-related defect interactions in the near-surface region of plasma-exposed tungsten}, + volume = {128}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/abs/10.1063/5.0023356}, + doi = {10.1063/5.0023356}, + number = {16}, + urldate = {2021-05-19}, + journal = {Journal of Applied Physics}, + author = {Weerasinghe, Asanka and Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, + month = oct, + year = {2020}, + note = {Publisher: American Institute of Physics}, + keywords = {mechanical properties}, + pages = {165109}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\FPEFZ6GU\\5.html:text/html}, } -@article{de_temmerman_effect_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Effect of high-flux {H}/{He} plasma exposure on tungsten damage due to transient heat loads}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514006758}, - doi = {10.1016/j.jnucmat.2014.09.075}, - abstract = {The thermal shock behaviour of tungsten exposed to high-flux plasma is studied using a high-power laser. The cases of laser-only, sequential laser and hydrogen (H) plasma and simultaneous laser plus H plasma exposure are studied. H plasma exposure leads to an embrittlement of the material and the appearance of a crack network originating from the centre of the laser spot. Under simultaneous loading, significant surface melting is observed. In general, H plasma exposure lowers the heat flux parameter (FHF) for the onset of surface melting by ∼25\%. In the case of He-modified (fuzzy) surfaces, strong surface deformations are observed already after 1000 laser pulses at moderate FHF=19MJm−2s−1/2, and a dense network of fine cracks is observed. These results indicate that high-fluence ITER-like plasma exposure influences the thermal shock properties of tungsten, lowering the permissible transient energy density beyond which macroscopic surface modifications begin to occur.}, - language = {en}, - urldate = {2019-11-21}, - journal = {Journal of Nuclear Materials}, - author = {De Temmerman, G. and Morgan, T. W. and van Eden, G. G. and de Kruif, T. and Wirtz, M. and Matejicek, J. and Chraska, T. and Pitts, R. A. and Wright, G. M.}, - month = aug, - year = {2015}, - keywords = {Experiment, Fuzz}, - pages = {198--201}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZT9DUUYP\\S0022311514006758.html:text/html;De Temmerman et al. - 2015 - Effect of high-flux HHe plasma exposure on tungst.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CAPGFGZT\\De Temmerman et al. - 2015 - Effect of high-flux HHe plasma exposure on tungst.pdf:application/pdf}, +@article{weerasinghe_elastic_2020, + title = {Elastic {Properties} of {Plasma}-{Exposed} {Tungsten} {Predicted} by {Molecular}-{Dynamics} {Simulations}}, + volume = {12}, + issn = {1944-8244}, + url = {https://doi.org/10.1021/acsami.0c01381}, + doi = {10.1021/acsami.0c01381}, + abstract = {We report results of systematic molecular-dynamics computations of the elastic properties of single-crystalline tungsten containing structural defects, voids and overpressurized He nanobubbles, related to plasma exposure of tungsten serving as a plasma-facing component (PFC) in nuclear fusion devices. Our computations reveal that the empty voids are centers of dilatation resulting in the development of tensile stress in the tungsten matrix, whereas He-filled voids (nanobubbles) introduce compressive stress in the plasma-exposed tungsten. We find that the dependence of the elastic moduli of plasma-exposed tungsten, namely, the bulk, Young, and shear modulus, on its void fraction follows a universal exponential scaling relation. We also find that the elastic moduli of plasma-exposed tungsten soften substantially as a function of He content in the tungsten matrix, following an exponential scaling relation; this He-induced exponential softening is in addition to the softening caused in the matrix with increasing temperature. A systematic characterization of the dependence of the elastic moduli on the He bubble size reveals that He bubble growth significantly affects both the bulk modulus and the Poisson ratio of plasma-exposed tungsten, while its effect on the Young and shear moduli of the plasma-exposed material is weak. Our findings contribute directly to the development of a structure–property database that is required for the predictive modeling of the dynamical response of PFCs in nuclear fusion devices.}, + number = {19}, + urldate = {2021-05-19}, + journal = {ACS Applied Materials \& Interfaces}, + author = {Weerasinghe, Asanka and Wirth, Brian D. and Maroudas, Dimitrios}, + month = may, + year = {2020}, + note = {Publisher: American Chemical Society}, + keywords = {mechanical properties}, + pages = {22287--22297}, } -@article{skinner_recent_2008, - title = {Recent advances on hydrogen retention in {ITER}'s plasma-facing materials: beryllium, carbon, and tunsgten}, - volume = {54}, - abstract = {Management of tritium inventory remains one of the grand challenges in the development of fusion energy, and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the International Atomic Energy Agency organized a Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001–2006. This dealt with hydrogenic retention in ITER’s plasma-facing materials—Be, C, and W—and in compounds (mixed materials) of these elements as well as tritium removal techniques. The results of the CRP are summarized in this paper together with recommendations for ITER. Basic parameters of diffusivity, solubility, and trapping in Be, C, and W are reviewed. For Be, the development of open porosity can account for transient hydrogenic pumping, but long-term retention will be dominated by codeposition. Codeposition is also the dominant retention mechanism for carbon and remains a serious concern for both Be- and C-containing layers. Hydrogenic trapping in unirradiated tungsten is low but will increase with ion and neutron damage. Mixed materials will be formed in a tokamak, and these can also retain significant amounts of hydrogen isotopes. Oxidative and photonbased techniques for detritiation of plasma-facing components are described.}, +@article{chen_effects_2020, + title = {Effects of elastic softening and helium accumulation kinetics on surface morphological evolution of plasma-facing tungsten}, + volume = {61}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/abbf64}, + doi = {10.1088/1741-4326/abbf64}, + abstract = {Based on a continuous-domain model, capable of accessing the spatiotemporal scales relevant to fuzz formation on the surface of plasma-facing component (PFC) tungsten, we report self-consistent simulation results that elucidate the effects of elastic softening and helium (He) accumulation kinetics on the surface morphological response of PFC tungsten. The model accounts for the softening of the elastic moduli in the near-surface region of PFC tungsten, including both thermal softening at high temperature and softening due to He accumulation upon He implantation. The dependence of the elastic moduli on the He content follows an exponential scaling relation predicted by molecular-dynamics simulations, while the He content in the near-surface region of PFC tungsten evolves according to a first-order saturation kinetics, consistent with experimental and simulation results reported in the literature. We establish that this elastic softening accelerates both nanotendril growth on the PFC surface and the onset of fuzz formation. We also explore the role of the rate of He accumulation to a saturation level in the near-surface region of irradiated tungsten in the onset of fuzz formation. For PFC tungsten surfaces such as W(110) where, under typical irradiation conditions, the characteristic time scale for stress-driven surface diffusion is comparable to the characteristic time scale for He accumulation, we find that accelerating the rate of He accumulation accelerates the growth rate of nanotendrils emanating from the surface. Additionally, we present a systematic parametric study of the PFC surface morphological response to explore its dependence on the He accumulation kinetics that is controlled by the irradiation conditions for low-energy implantation. Finally, we introduce an incubation time for nanotendril growth on the PFC surface, a concept equivalent to that of incubation fluence discussed in the literature, to predict and explain the minimum exposure time required to observe fuzz formation on PFC tungsten surfaces.}, language = {en}, - author = {Skinner, C H and Haasz, A A and Alimov, V Kh and Bekris, N and Causey, R A and Clark, R E H and Coad, J P and Davis, J W and Doerner, R P and Mayer, M and Pisarev, A and Roth, J and Tanabe, T}, - year = {2008}, - pages = {55}, - file = {Skinner et al. - 2008 - Recent advances on hydrogen retention in ITER's pl.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BLIUUNI4\\Skinner et al. - 2008 - Recent advances on hydrogen retention in ITER's pl.pdf:application/pdf}, + number = {1}, + urldate = {2021-05-19}, + journal = {Nuclear Fusion}, + author = {Chen, Chao-Shou and Dasgupta, Dwaipayan and Weerasinghe, Asanka and Wirth, Brian D. and Maroudas, Dimitrios}, + month = nov, + year = {2020}, + note = {Publisher: IOP Publishing}, + keywords = {mechanical properties}, + pages = {016016}, } -@article{becquart_density_2009, - series = {Fusion {Reactor} {Materials}}, - title = {A density functional theory assessment of the clustering behaviour of {He} and {H} in tungsten}, - volume = {386-388}, +@article{wei_better_2020, + title = {A better nanochannel tungsten film in releasing helium atoms}, + volume = {532}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311508008179}, - doi = {10.1016/j.jnucmat.2008.12.085}, - abstract = {We have used density functional theory based ab initio calculations to investigate the tendency of He and H to form clusters. For both species the most stable interstitial configuration is in a tetrahedral site, however their clustering tendencies are totally different. The He–He interaction is purely elastic in nature and as such highly binding at close separation distances. The H–H interaction on the other hand is almost negligible since the elastic binding effect is compensated for by the change in effective position of the H states in the density of states. He atoms always bond more strongly to HexHy complexes in a vacancy than H atoms.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311519311225}, + doi = {10.1016/j.jnucmat.2020.152044}, + abstract = {Discovering highly radiation resistant plasma facing materials (PFM) is an urgent target for nuclear fusion reactor. In our previous work, a new PFM (nanochannel tungsten film) that consists of many tungsten crystal columns was found having excellent radiation tolerant properties. In the present work, three tungsten columns whose top surfaces are \{100\}, \{110\} and \{111\} -oriented were studied by molecular dynamics simulations and density functional theory calculations. We find that the tungsten columns whose top surfaces are \{100\}-oriented retain fewer helium atoms than the tungsten columns whose top surfaces are \{110\} or \{111\}-oriented. Moreover, the microstructural changes of tungsten columns whose top surfaces are \{100\}-oriented are smaller than others after high helium fluence exposure, which indicates that the nanochannel tungsten film maybe more suitable than bulk tungsten for plasma facing material in releasing helium atoms and delaying the formation of “fuzz” structure. The results reported here can help us to design a better radiation resistant plasma facing material in the future.}, language = {en}, - urldate = {2019-10-30}, + urldate = {2021-05-17}, journal = {Journal of Nuclear Materials}, - author = {Becquart, Charlotte S. and Domain, Christophe}, + author = {Wei, Guo and Li, Jingwen and Li, Yonggang and Deng, Huiqiu and Jiang, Changzhong and Ren, Feng}, month = apr, - year = {2009}, - keywords = {Density Functional Theory}, - pages = {109--111}, - file = {Becquart et Domain - 2009 - A density functional theory assessment of the clus.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YUEFIHCN\\Becquart et Domain - 2009 - A density functional theory assessment of the clus.pdf:application/pdf}, + year = {2020}, + pages = {152044}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HNIQ4AVZ\\Wei et al. - 2020 - A better nanochannel tungsten film in releasing he.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\Y45J6E62\\S0022311519311225.html:text/html}, } -@phdthesis{hodille_study_2016, - title = {Study and modeling of the deuterium trapping in {ITER} relevant materials}, - url = {https://tel.archives-ouvertes.fr/tel-01477426}, - abstract = {During ITER operation, important flux of Hydrogen Isotopes (HIs) constituting the fuel interact with the plasma facing components (PFC) of the machine. In the case of tungsten (W) making the divertor which is the most exposed area to the plasma wall interaction, the incident flux can be implanted and diffuse inside the bulk material inducing a trapping of the fuel. To safety issue, the tritium inventory retained in ITER’s PFC is limited. In addition, the outgassing of the fuel during plasma operation can impact the edge plasma control. The aim of this PhD project is first to determined relevant trapping parameters of the fuel in W (detrapping energies/temperatures and trap concentrations) by modelling experimental results. The simulations of experimental results shows that under specific condition, the HI implantation can induce the formation of mono-vacancies containing impurities. In addition to this induced trap, 2 intrinsic traps are present in W. This 3 traps retain HIs up to 700 K. Finally, it has been shown that the damaged W by heavy ions or neutrons contains dislocations, dislocation loops and cavities that can trap HIs up to 1000 K. After determining the fuel retention properties of W, the HIs retention during ITER operation is estimated. During this operation, the PFC temperature reaches around 1000 K so the simulations show that the damaged W retains much more HIs than the undamaged W.}, +@article{wei_understanding_2019, + title = {Understanding the release of helium atoms from nanochannel tungsten: a molecular dynamics simulation}, + volume = {59}, + issn = {0029-5515}, + shorttitle = {Understanding the release of helium atoms from nanochannel tungsten}, + url = {https://doi.org/10.1088/1741-4326/ab14c7}, + doi = {10.1088/1741-4326/ab14c7}, + abstract = {The design of highly radiation-tolerant plasma-facing materials (PFMs) is of great importance for fusion reactors. Our recent experiments have shown that nanochannel tungsten (W) films have clearly superior radiation tolerance properties. In the present work, helium clustering and release from nanochannel tungsten were studied by molecular dynamics simulations. The effects of temperature and vacancy concentration on the helium release from a tungsten cylinder were investigated. Our results show that nanochannel W that consists of thin W cylinders releases He atoms more quickly than bulk W with flat surfaces, thus greatly reducing the He concentration and suppressing the formation and growth of He bubbles, which leads to increased radiation tolerance. Moreover, the microstructural changes due to increasing He fluence are smaller in nanochannel W than those in bulk W. Although vacancies in nanochannel W will trap He atoms, the nanochannel W also has a stronger tendency to stabilize helium retention than bulk W. The mechanism of helium release from nanochannel W was also examined. The results reported here are beneficial for guiding future work in the design of radiation resistant PFMs.}, language = {en}, + number = {7}, + urldate = {2021-05-17}, + journal = {Nuclear Fusion}, + author = {Wei, Guo and Ren, Feng and Fang, Jingzhong and Hu, Wangyu and Gao, Fei and Qin, Wenjing and Cheng, Tao and Wang, Yongqiang and Jiang, Changzhong and Deng, Huiqiu}, + month = jun, + year = {2019}, + note = {Publisher: IOP Publishing}, + pages = {076020}, +} + +@article{hammond_large-scale_2018, + title = {Large-scale atomistic simulations of low-energy helium implantation into tungsten single crystals}, + volume = {144}, + issn = {1359-6454}, + url = {http://www.sciencedirect.com/science/article/pii/S1359645417308315}, + doi = {10.1016/j.actamat.2017.09.061}, + abstract = {Large-scale molecular dynamics simulations of post-implantation helium behavior in plasma-facing tungsten single crystals reveal orientation-dependent depth profiles, surface evolution patterns, and other crystallographic and diffusion-related characteristics of helium behavior in tungsten during the first microsecond. The flux of implanted helium atoms studied, Γ ≈ 4 × 1025 m−2 s−1, is about one order of magnitude larger than that expected in ITER, the experimental fusion reactor currently being constructed in France. With simulation times on the order of 1 μs, these results serve to discover the mechanisms involved in surface evolution as well as to serve as benchmarks for coarse-grained simulations such as kinetic Monte Carlo and continuum-scale drift–reaction–diffusion cluster dynamics simulations. The findings of our large-scale simulations are significant due to diminished finite-size effects and the longer times reached (corresponding to higher fluences). Specifically, our findings are drastically different from findings published previously in the literature for (001) surfaces under a helium flux of Γ ∼ 1028 m−2 s−1, which is typical of smaller size and shorter time atomistic simulations. In particular, this study highlights the atomic-scale materials processes relevant to helium entrapment and transport in metals, which have implications not only for nuclear fusion–relevant processes, but also helium-induced embrittlement in irradiated materials such as hospital equipment and fission reactor materials.}, urldate = {2019-10-07}, - school = {Aix-Marseille}, - author = {Hodille, Etienne}, - month = nov, - year = {2016}, - keywords = {Macroscopic rate equations}, - file = {Hodille - 2016 - Study and modeling of the deuterium trapping in IT.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Q2U7IN23\\Hodille - 2016 - Study and modeling of the deuterium trapping in IT.pdf:application/pdf}, + journal = {Acta Materialia}, + author = {Hammond, Karl D. and Blondel, Sophie and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, + month = feb, + year = {2018}, + keywords = {Molecular dynamics, Tungsten, Helium, Molecular Dynamics, Nuclear fusion, Plasma-facing material}, + pages = {561--578}, + annote = { +MD simulations of He implantation in W single crystals. +Investigation of orientation effects on depth profiles. +Very high flux (one order of magnitude larger than in ITER). +Simulation times of 1 microsecond. +Lattice and reflexion parameters are given. +Large clusters are seen at 5 nm. +Not a significant change in depth profile after 100 microseconds with different orientations. +Counting of He atoms per bubble. +}, + file = {Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:D\:\\Logiciels\\data_zotero\\storage\\6Z7V7EV2\\Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\75S2EHRZ\\Hammond et al. - 2018 - Large-scale atomistic simulations of low-energy he.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\H28LWS3B\\S1359645417308315.html:text/html}, } -@article{ning_improved_2012, - title = {An {Improved} {Cluster} {Dynamics} {Model} {For} {Hydrogen} {Retention} {In} {Tungsten}}, - url = {https://www.semanticscholar.org/paper/An-Improved-Cluster-Dynamics-Model-For-Hydrogen-In-Ning-Li/75873a7dd89cabc7474c953e267bb93105c3e705}, - doi = {10.1142/S0129183112500428}, - abstract = {An improved cluster dynamics model has been developed for studying the behaviors of hydrogen retention in tungsten under hydrogen ions irradiation. In addition to different types of objects, adopting up-to-date parameters and complex reaction processes, we newly introduce ion-induced and natural defects into our model. This improved model programmed in IRadMat2 could describe very well the depth distributions and the amounts of hydrogen retained in tungsten under different radiation conditions. The calculated results agree with the experimental ones much better than the previous model, especially for the depth-distribution of D retained in W, which imply that this model is applicable to the evolution of defects especially for low energy high flux ions irradiated on plasma-facing materials.}, - journal = {International Journal of Modern Physics C}, - author = {Ning, Ruola and Li, Yon Gan and Zhou, Weihong and Zeng, Zhi and Ju, Xin}, - year = {2012}, - keywords = {Cluster dynamics}, - file = {Ning et al. - 2012 - An Improved Cluster Dynamics Model For Hydrogen Re.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DUALYV4S\\Ning et al. - 2012 - An Improved Cluster Dynamics Model For Hydrogen Re.pdf:application/pdf}, +@article{temmerman_influence_2018, + title = {The influence of plasma-surface interaction on the performance of tungsten at the {ITER} divertor vertical targets}, + volume = {60}, + issn = {0741-3335}, + url = {https://doi.org/10.1088%2F1361-6587%2Faaaf62}, + doi = {10.1088/1361-6587/aaaf62}, + abstract = {The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed to high fluxes of low-energy particles (e.g. H, D, T, He, Ne and/or N). Combined with long-pulse operations, this implies fluences well in excess of the highest values reached in today’s tokamak experiments. Shaping of the individual monoblock top surface and tilting of the vertical targets for leading-edge protection lead to an increased surface heat flux, and thus increased surface temperature and a reduced margin to remain below the temperature at which recrystallization and grain growth begin. Significant morphology changes are known to occur on W after exposure to high fluences of low-energy particles, be it H or He. An analysis of the formation conditions of these morphology changes is made in relation to the conditions expected at the vertical targets during different phases of operations. It is concluded that both H and He-related effects can occur in ITER. In particular, the case of He-induced nanostructure (also known as ‘fuzz’) is reviewed. Fuzz formation appears possible over a limited region of the outer vertical target, the inner target being generally a net Be deposition area. A simple analysis of the fuzz growth rate including the effect of edge-localized modes (ELMs) and the reduced thermal conductivity of fuzz shows that the fuzz thickness is likely to be limited by the occurrence of annealing during ELM-induced thermal excursions. Not only the morphology, but the material mechanical and thermal properties can be modified by plasma exposure. A review of the existing literature is made, but the existing data are insufficient to conclude quantitatively on the importance and extent of these effects for ITER. As a consequence of the high surface temperatures in ITER, W recrystallization is an important effect to consider, since it leads to a decrease in material strength. An approach is proposed here to develop an operational budget for the W material, i.e. the time the divertor material can be operated at a given temperature before a significant fraction of the material is recrystallized. In general, while it is clear that significant surface damage can occur during ITER operations, the tolerable level of damage in terms of plasma operations currently remains unknown.}, + language = {en}, + number = {4}, + urldate = {2020-06-03}, + journal = {Plasma Physics and Controlled Fusion}, + author = {Temmerman, G. De and Hirai, T. and Pitts, R. A.}, + month = mar, + year = {2018}, + note = {Publisher: IOP Publishing}, + pages = {044018}, + file = {De Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:D\:\\Logiciels\\data_zotero\\storage\\MTX484WV\\De Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf;IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\L9V2JQ2K\\Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf;IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\6ZPP7I4S\\Temmerman et al. - 2018 - The influence of plasma-surface interaction on the.pdf:application/pdf}, } -@phdthesis{muthali_electronic_2019, - title = {Electronic structure calculations and thermodynamic models for energy-producing systems}, +@article{calderoni_measurement_2008, + title = {Measurement of tritium permeation in flibe ({2LiF}–{BeF2})}, + volume = {83}, + issn = {09203796}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379608000926}, + doi = {10.1016/j.fusengdes.2008.05.016}, + abstract = {This paper reports on the experimental investigation of tritium permeation in flibe (2LiF-BeF2) at the Safety and Tritium Applied Research facility of the Idaho National Laboratory. A stainless steel cell formed by two independent volumes separated by a 2mm thick nickel membrane is maintained at temperatures between 500 and 700 degrees Celsius. A controlled amount of T2 gas is flown in excess of argon in the source volume in contact with the bottom side of the nickel membrane, while a layer of molten salt is in contact with the top side. The tritium permeating above the liquid surface is carried by an argon flow to a diagnostic system comprised of a quadrupole mass spectrometer, a gas chromatographer and a proportional counter. Tritium permeability in flibe as a function of temperature is determined by the measured permeation flow rates reached in steady-state conditions, while the diffusivity is determined by fitting the transient process with the analytical solution for the diffusion process. As a result, the solubility of tritium in flibe as a function of temperature is also determined.}, language = {en}, - school = {Aix-Marseille}, - author = {Muthali, Ajmalghan}, - month = sep, - year = {2019}, - keywords = {Density Functional Theory}, - file = {Muthali - Electronic structure calculations and thermodynami.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SWIUSS7F\\Muthali - Electronic structure calculations and thermodynami.pdf:application/pdf}, + number = {7-9}, + urldate = {2021-05-05}, + journal = {Fusion Engineering and Design}, + author = {Calderoni, P. and Sharpe, P. and Hara, M. and Oya, Y.}, + month = dec, + year = {2008}, + keywords = {Fusion, Solubility, Tritium, Molten salt, Diffusivity}, + pages = {1331--1334}, + file = {Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:D\:\\Logiciels\\data_zotero\\storage\\Q8GBT577\\Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SN5FMKAY\\Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\LYH674HW\\S0920379608000926.html:text/html}, } -@article{hammond_helium_2017, - title = {Helium, hydrogen, and fuzz in plasma-facing materials}, - volume = {4}, - issn = {2053-1591}, - doi = {10.1088/2053-1591/aa8c22}, - abstract = {Tungsten, the primary material under consideration as the divertor material in magnetic-confinement nuclear fusion reactors, has been known for the last decade to form ‘fuzz’—a layer of microscopic, high-void-fraction features on the surface—after only a few hours of exposure to helium plasma. Fuzz has also been observed in molybdenum, tantalum, and several other metals. Helium bubbles in tungsten and other metals are also known to change the hardness of the surface, accumulate at grain boundaries and dislocations, and increase hydrogen isotope retention. This article reviews helium- and hydrogen-induced surface evolution, including fuzz formation, in tungsten and other plasma-facing materials, as well as modeling and experimental efforts that have been undertaken to understand the mechanisms of fuzz formation, helium and hydrogen transport in plasma-facing materials, and relevant atomic-scale and electronic effects relevant to plasma-facing materials.}, +@article{faney_spatially_2015, + title = {Spatially dependent cluster dynamics model of {He} plasma surface interaction in tungsten for fusion relevant conditions}, + volume = {55}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/55/1/013014}, + doi = {10.1088/0029-5515/55/1/013014}, + abstract = {In fusion reactors, plasma facing components (PFC) and, in particular, the divertor will be irradiated with high fluxes of low-energy (∼100 eV) helium and hydrogen ions. Tungsten is one of the leading candidate divertor materials for ITER and DEMO fusion reactors. However, the behaviour of tungsten under high dose, coupled helium/hydrogen exposure remains to be fully understood. The PFC response and performance changes are intimately related to microstructural changes, such as the formation of point defect clusters, helium and hydrogen bubbles or dislocation loops. Computational materials' modelling results are described here that investigate the mechanisms controlling microstructural evolution in tungsten. The aim of this study is to understand and predict sub-surface helium bubble growth under high flux helium ion implantation (∼1022 m−2 s−1) at high temperatures ({\textgreater}1000 K). We report results from a spatially dependent cluster dynamics model based on reaction–diffusion rate theory to describe the evolution of the microstructure under these conditions. The key input parameters to the model (diffusion coefficients, migration and binding energies, initial defect production) are determined from a combination of atomistic modelling and available experimental data. The results are in good agreement with results of an analytical model that is presented in a separate paper. In particular, it is found that the sub-surface evolution with respect to bubble size and concentration of the helium bubbles strongly depends on the flux and temperature.}, + language = {en}, + number = {1}, + urldate = {2019-10-28}, + journal = {Nuclear Fusion}, + author = {Faney, T. and Krasheninnikov, S. I. and Wirth, B. D.}, + year = {2015}, + keywords = {Cluster dynamics, Bubble}, + pages = {013014}, + annote = { +1D modelling of He transport in W. +Cluster dynamics. +Many reactions are described. +Expressions for radii. +2 test cases: + +W tendril of a few tens of nm and +semi infinite slab. + + +Profiles shown (could be reproduced). +Concentration of He clusters inferior to He concentration by 5 orders of magnitude. +Concentration of He bubbles similar to He concentration after a certain amount of time. +Influence of temperature, helium flux investigated. +Comparison with analytical model. +He bubbles act as a diffusion plug as it stops diffusion. +}, + file = {Faney et al. - 2014 - Spatially dependent cluster dynamics model of He p.pdf:D\:\\Logiciels\\data_zotero\\storage\\K7KCEVWB\\Faney et al. - 2014 - Spatially dependent cluster dynamics model of He p.pdf:application/pdf}, +} + +@article{niu_effect_2021, + title = {Effect of temperature on the growth and surface bursting of {He} nano-bubbles in {W} under fusion-relevant {He} ion irradiations}, + volume = {163}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379620307079}, + doi = {10.1016/j.fusengdes.2020.112159}, + abstract = {Under fusion-relevant He+ irradiations, the W surface temperature is one of the most important parameters for controlling the fuzz growth over the W divertor targets, which is associated with the surface bursting of He nano-bubbles. Using He reaction rate model in W, we investigate the effect of temperature on the growth and surface bursting of He nano-bubbles under low-energy (100 eV) and large-flux (∼1022/m2⋅s) He+ irradiations. Increasing the irradiation temperature from 750 to 2500 K leads to a significant change in both the radius of He nano-bubbles and He retention. At an elevated temperature, He solute atoms prefer to rapidly diffuse into He nano-bubbles, thus affecting their concentration, growth and surface bursting. The decrease in He retention is attributed to an increase in the hop rate of solute He atoms in the W top layer, resulting in the significant He release from the W surface. The radius and density of He nano-bubbles calculated by our model are consistent with our experimental observation.}, language = {en}, - number = {10}, - urldate = {2019-10-25}, - journal = {Materials Research Express}, - author = {Hammond, Karl D.}, - month = oct, - year = {2017}, - keywords = {Bubble, Experiment, Fuzz}, - pages = {104002}, - file = {Hammond - 2017 - Helium, hydrogen, and fuzz in plasma-facing materi.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EEYZCISS\\Hammond - 2017 - Helium, hydrogen, and fuzz in plasma-facing materi.pdf:application/pdf}, + urldate = {2021-05-05}, + journal = {Fusion Engineering and Design}, + author = {Niu, Chunjie and Zhang, Yang and Cui, Yunqiu and Li, Xiaoping and Liu, Weifeng and Ni, Weiyuan and Fan, Hongyu and Lu, Na and Benstetter, Günther and Lei, Guangjiu and Liu, Dongping}, + month = feb, + year = {2021}, + keywords = {Tungsten, Nuclear fusion, He ion irradiation, He nanobubble, Plasma facing materials}, + pages = {112159}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\RR228XVL\\Niu et al. - 2021 - Effect of temperature on the growth and surface bu.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KPGXQ4BR\\S0920379620307079.html:text/html}, } -@article{bernard_temperature_2017, - title = {Temperature impact on the micro structure of tungsten exposed to {He} irradiation in {LHD}}, - volume = {484}, +@article{pillai_first_2021, + title = {First steps toward predicting corrosion behavior of structural materials in molten salts}, + volume = {546}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311516306560}, - doi = {10.1016/j.jnucmat.2016.10.040}, - abstract = {A new temperature controlled material probe was designed for the exposure of tungsten samples to helium plasma in the LHD. Samples were exposed to estimated fluences of ∼1023 m−2 and temperatures ranging from 65 to 600 °C. Transmission Electron Microscopy analysis allowed the study of the impact of He irradiation under high temperatures on tungsten micro structure for the first time in real-plasma exposure conditions. Both dislocation loops and bubbles appeared from low to medium temperatures and saw an impressive increase of size (factor 4 to 6) most probably by coalescence as the temperature reaches 600 °C, with 500 °C appearing as a threshold for bubble growth. Annealing of the samples up to 800 C highlighted the stability of the dislocation damages formed by helium irradiation at high surface temperature, as bubbles and dislocation loops seem to conserve their characteristics. Additional studies on cross-sections showed that bubbles were formed much deeper (70–100 nm) than the heavily damaged surface layer (10–20 nm), raising concern about the impact on the material mechanical properties conservation and potential additional trapping of hydrogen isotopes.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311520313635}, + doi = {10.1016/j.jnucmat.2020.152755}, + abstract = {To address the need for physics-based models to predict corrosion behavior of materials in molten salts, the current work proposes potential methods to aid in selection of optimum materials for structural components in molten salt powered technologies. In the present work, the role of alloy thermodynamics and kinetics on governing corrosion rates of Ni-based alloys will be discussed combining experimental and computational methods. A few strategies are presented to quantify corrosion rates of Ni-based materials isothermally exposed in purified KCl-MgCl2 salts at 600 ∘ C-800 ∘ C. The influence of capsule material, potential corrosion products and role of alloy composition on the observed corrosion rates was discussed with coupled thermodynamic-kinetic models. Larger depths of corrosion attack were observed in alloy 230 specimens compared to other alloys under similar conditions was attributed to the much higher chemical activity of Cr in the alloy that results in a larger Cr chemical potential gradient.}, language = {en}, - urldate = {2019-10-29}, + urldate = {2021-05-05}, journal = {Journal of Nuclear Materials}, - author = {Bernard, Elodie and Sakamoto, Ryuichi and Tokitani, Masayuki and Masuzaki, Suguru and Hayashi, Hiromi and Yamada, Hiroshi and Yoshida, Naoaki}, - month = feb, - year = {2017}, - keywords = {Bubble, Experiment, Fuzz}, - pages = {24--29}, - file = {Bernard et al. - 2017 - Temperature impact on the micro structure of tungs.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3QVHN3W5\\Bernard et al. - 2017 - Temperature impact on the micro structure of tungs.pdf:application/pdf}, + author = {Pillai, R. and Raiman, S. S. and Pint, B. A.}, + month = apr, + year = {2021}, + keywords = {Corrosion rates, Coupled thermodynamic-kinetic modeling, Molten salts, Ni-based alloys}, + pages = {152755}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\CE7L7CM4\\Pillai et al. - 2021 - First steps toward predicting corrosion behavior o.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CICPY3FE\\S0022311520313635.html:text/html}, } -@article{wirtz_influence_2016, - title = {Influence of helium induced nanostructures on the thermal shock performance of tungsten}, - volume = {9}, +@article{de_temmerman_data_2021, + title = {Data on erosion and hydrogen fuel retention in {Beryllium} plasma-facing materials}, + volume = {27}, issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179115301198}, - doi = {10.1016/j.nme.2016.07.002}, - abstract = {Experiments were performed in the linear plasma device PSI-2 in order to investigate the synergistic effects of combined steady-state He-plasma and thermal shock exposure. Tungsten produced according to the ITER material specifications by Plansee SE, Austria, was loaded sequentially and simultaneously by steady-state He plasma and transient thermal loads induced by a laser beam. All tungsten samples were exposed to helium plasma for 40min at a base temperature of ca. 850°C and a flux of ca. 2.8×1022m−2s−1. Before, during and after the plasma exposure 1000 thermal shock pulses with a pulse duration of 1ms and a power density 0.76GW/m² were applied on the samples. The thermal shock exposure before and after plasma exposure was done at room temperature in order to investigate helium induced surface effects also within cracks. The obtained results show that the combination of He plasma with transient thermal shock events results in a severe modification such as reduced height or agglomeration of the sub-surface He-bubbles and of the created nanostructures, i.e. W-fuzz.}, - urldate = {2019-10-07}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121000740}, + doi = {10.1016/j.nme.2021.100994}, + abstract = {ITER will use beryllium as a plasma-facing material in the main chamber, covering a total surface area of about 620 m2. Given the importance of beryllium erosion and co-deposition for tritium retention in ITER, significant efforts have been made to understand the behaviour of beryllium under fusion-relevant conditions with high particle and heat loads. This paper provides a comprehensive report on the state of knowledge of beryllium behaviour under fusion-relevant conditions: the erosion mechanisms and their consequences, beryllium migration in JET, fuel retention and dust generation. The paper reviews basic laboratory studies, advanced computer simulations and experience from laboratory plasma experiments in linear simulators of plasma–wall interactions and in controlled fusion devices using beryllium plasma-facing components. A critical assessment of analytical methods and simulation codes used in beryllium studies is given. The overall objective is to review the existing set of data with a broad literature survey and to identify gaps and research needs to broaden the database for ITER.}, + language = {en}, + urldate = {2021-04-28}, journal = {Nuclear Materials and Energy}, - author = {Wirtz, M. and Berger, M. and Huber, A. and Kreter, A. and Linke, J. and Pintsuk, G. and Rasinski, M. and Sergienko, G. and Unterberg, B.}, - month = dec, - year = {2016}, - keywords = {Bubble, Experiment, Fuzz}, - pages = {177--180}, - file = {Wirtz et al. - 2016 - Influence of helium induced nanostructures on the .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8B7FGA4D\\Wirtz et al. - 2016 - Influence of helium induced nanostructures on the .pdf:application/pdf}, + author = {De Temmerman, Gregory and Heinola, Kalle and Borodin, Dmitriy and Brezinsek, Sebastijan and Doerner, Russell P. and Rubel, Marek and Fortuna-Zaleśna, Elżbieta and Linsmeier, Christian and Nishijima, Daisuke and Nordlund, Kai and Probst, Michael and Romazanov, Juri and Safi, Elnaz and Schwarz-Selinger, Thomas and Widdowson, Anna and Braams, Bastiaan J. and Chung, Hyun-Kyung and Hill, Christian}, + month = jun, + year = {2021}, + keywords = {Beryllium, Plasma-facing material, Controlled fusion, Dust, Erosion–deposition}, + pages = {100994}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FIZVHXTA\\De Temmerman et al. - 2021 - Data on erosion and hydrogen fuel retention in Ber.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BLTG9QN2\\S2352179121000740.html:text/html}, } -@article{zenobia_formation_2009, - title = {Formation and retention of surface pores in helium-implanted nano-grain tungsten for fusion reactor first-wall materials and divertor plates}, +@article{parish_grain_2017, + title = {Grain orientations and grain boundaries in tungsten nonotendril fuzz grown under divertor-like conditions}, + volume = {127}, + issn = {1359-6462}, + url = {https://www.sciencedirect.com/science/article/pii/S1359646216304468}, + doi = {10.1016/j.scriptamat.2016.09.018}, + abstract = {We grew nanotendril “fuzz” on tungsten via plasma exposure and performed transmission Kikuchi diffraction (tKD) in scanning electron microscopy of isolated nanotendrils. 900°C, 1023He/m2sec, 4×1026He/m2 exposure of tungsten produced a deep and fully developed nanotendril mat. tKD of isolated nanotendrils indicated that there was no preferred crystallographic direction oriented along the long axes of the tendrils, and the grain boundary character showed slightly preferential orientations. Tendril growth is sufficiently non-equilibrium to prevent any preference of growth direction to manifest measurably, and that new high-angle boundaries (with new grains and grain-growth axes) nucleate randomly along the tendrils during growth.}, + language = {en}, + urldate = {2021-04-20}, + journal = {Scripta Materialia}, + author = {Parish, Chad M. and Wang, Kun and Doerner, Russel P. and Baldwin, Matthew J.}, + month = jan, + year = {2017}, + keywords = {Tungsten, Fusion, Fusion energy, Plasma simulation, Transmission Kikuchi diffraction}, + pages = {132--135}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DVFSAUKK\\Parish et al. - 2017 - Grain orientations and grain boundaries in tungste.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MGF7RBXX\\S1359646216304468.html:text/html}, +} + +@article{alimov_surface_2009, + title = {Surface morphology and deuterium retention in tungsten exposed to low-energy, high flux pure and helium-seeded deuterium plasmas}, volume = {T138}, - issn = {1402-4896}, - url = {https://iopscience.iop.org/article/10.1088/0031-8949/2009/T138/014049}, - doi = {10.1088/0031-8949/2009/T138/014049}, - abstract = {Nano-grain W samples were implanted with 30 keV 3He ions to fluences of 1021, 1022 and 1023 He m−2, at temperatures ranging from approximately 1273 to 1423 K. One specimen was implanted with 30 keV 4He ions at 1273 K to 1024 He m−2. Scanning electron microscopy showed the onset of visible surface pore formation occurred between approximately 1021 and 1022 He+ m−2 and increased with higher implant fluences, eventually resulting in a ‘coral-like’ surface structure. Focused ion beam analysis revealed the depth of visible subsurface pores increased with higher doses, extending below the surface to a maximum value of approximately 730 nm. Using 3He(d, p)4He nuclear reaction analysis on 3He+ implanted specimens retained helium fluences were found to range from 4.0×1020 to 4.5×1021 He m−2. Each specimen sustained mass loss after implantation which was observed to increase with greater He+ dose.}, + issn = {0031-8949, 1402-4896}, + url = {https://iopscience.iop.org/article/10.1088/0031-8949/2009/T138/014048}, + doi = {10.1088/0031-8949/2009/T138/014048}, + abstract = {Blistering and deuterium retention in re-crystallized tungsten exposed to low-energy, high flux pure and helium-seeded D plasmas to a fluence of 1027 D m−2 have been examined with scanning electron microscopy, thermal desorption spectroscopy, and the D(3He, p)4He nuclear reaction at 3He energies varied from 0.69 to 4.0 MeV. In the case of exposure to pure D plasma (38 eV D−1), blisters with various shapes and sizes depending on the exposure temperature are found on the W surface. No blisters appear at temperatures above 700 K. The deuterium retention increases with the exposure temperature, reaching a maximum value of about 1022 D m−2 at 480 K, and then decreases as the temperature rises further. Seeding of 76 eV He ions into the D plasma significantly reduces the D retention at elevated temperatures and prevents formation of the blisters.}, language = {en}, - urldate = {2019-10-30}, + urldate = {2021-04-20}, journal = {Physica Scripta}, - author = {Zenobia, S. J. and Kulcinski, G. L.}, + author = {Alimov, V Kh and Shu, W M and Roth, J and Sugiyama, K and Lindig, S and Balden, M and Isobe, K and Yamanishi, T}, month = dec, year = {2009}, - keywords = {Bubble, Experiment, Fuzz}, - pages = {014049}, - file = {Zenobia et Kulcinski - 2009 - Formation and retention of surface pores in helium.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\N8952AGP\\Zenobia et Kulcinski - 2009 - Formation and retention of surface pores in helium.pdf:application/pdf}, + pages = {014048}, + file = {Alimov et al. - 2009 - Surface morphology and deuterium retention in tung.pdf:D\:\\Logiciels\\data_zotero\\storage\\IA48UPDI\\Alimov et al. - 2009 - Surface morphology and deuterium retention in tung.pdf:application/pdf}, } -@article{baldwin_effects_2009, - series = {Proceedings of the 18th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion} {Device}}, - title = {The effects of high fluence mixed-species (deuterium, helium, beryllium) plasma interactions with tungsten}, - volume = {390-391}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311509002566}, - doi = {10.1016/j.jnucmat.2009.01.247}, - abstract = {W targets are exposed to D2−Be, He, D2−He and D2−Be−He plasmas in the linear-plasma-device PISCES-B to simulate the conditions expected at W strike-points in an ITER all W metal divertor scenario. In D2−Be and He plasmas, target temperatures in the range 1070–1320K lead to surface layers of Be–W alloy or nano-structured W morphology, respectively, but below 900K, neither types of layer are found to form. Both processes have kinetics reminiscent of diffusion. Alloying kinetics are optimal when surface Be availability is maximized through the formation of a deposited Be over-layer. Nano-structured layer growth at 1120K is most rapid for incident He ion fluxes above 7×1021m−2s−1. In D2−0.1He plasmas, a mixture relevant to divertor exhaust, small Be or C fractions can significantly reduce nano-structure growth in favor of the formation of a mixed material Be−W alloy or C layer.}, +@misc{noauthor_effect_nodate, + title = {Effect of the presence of helium in tungsten on deuterium retention - {ScienceDirect}}, + url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/science/article/pii/S0022311521000969?via%3Dihub}, + urldate = {2021-04-20}, + file = {Effect of the presence of helium in tungsten on deuterium retention - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\6JQILEBL\\S0022311521000969.html:text/html}, +} + +@article{reza_thermal_2020, + title = {Thermal diffusivity degradation and point defect density in self-ion implanted tungsten}, + volume = {193}, + issn = {1359-6454}, + url = {https://www.sciencedirect.com/science/article/pii/S1359645420302214}, + doi = {10.1016/j.actamat.2020.03.034}, + abstract = {Using transient grating spectroscopy (TGS) we measure the thermal diffusivity of tungsten exposed to different levels of 20 MeV self-ion irradiation. Damage as low as 3.2 × 10−4 displacements per atom (dpa) causes a measurable reduction in thermal diffusivity. Doses of 0.1 dpa and above, up to 10 dpa, give a degradation of ∼55\% from the pristine value at room temperature. Using a kinetic theory model, the density of irradiation-induced point defects is estimated based on the measured changes in thermal diffusivity as a function of dose. These predictions are compared with point defect and dislocation loop densities observed in transmission electron microscopy (TEM). Molecular dynamics (MD) predictions are combined with the TEM observations to estimate the density of point defects associated with defect clusters too small to be probed by TEM. When these “invisible” defects are accounted for, the total point defect density agrees well with that estimated from TGS for a range of doses spanning 3 orders of magnitude. Kinetic theory modelling is also used to estimate the thermal diffusivity degradation expected due to TEM-visible and invisible defects. Finely distributed invisible defects appear to play a much more important role in the thermal diffusivity reduction than larger TEM-visible dislocation loops. This work demonstrates the capability of TGS, in conjunction with kinetic theory models, to provide rapid, quantitative insight into defect densities and property evolution in irradiated materials.}, language = {en}, - urldate = {2019-10-30}, - journal = {Journal of Nuclear Materials}, - author = {Baldwin, M. J. and Doerner, R. P. and Nishijima, D. and Tokunaga, K. and Ueda, Y.}, - month = jun, - year = {2009}, - keywords = {Experiment, Fuzz}, - pages = {886--890}, - file = {Baldwin et al. - 2009 - The effects of high fluence mixed-species (deuteri.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CDDWNY24\\Baldwin et al. - 2009 - The effects of high fluence mixed-species (deuteri.pdf:application/pdf}, + urldate = {2021-04-19}, + journal = {Acta Materialia}, + author = {Reza, Abdallah and Yu, Hongbing and Mizohata, Kenichiro and Hofmann, Felix}, + month = jul, + year = {2020}, + keywords = {Fusion materials, Point defects, Thermal conductivity, Transient grating spectroscopy}, + pages = {270--279}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EHQ8FRQ3\\Reza et al. - 2020 - Thermal diffusivity degradation and point defect d.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\Z94RE44L\\S1359645420302214.html:text/html}, } -@phdthesis{guterl_modeling_2015, - title = {Modeling of hydrogen isotopes retention in plasma-facing components for fusion applications}, - abstract = {Plasma-material interactions might strongly affect plasma performances and life-time of future magnetic fusion devices. For example, retention and recycling of hydrogen isotopes in plasma-facing components (PFC) may lead to dynamics plasma-material interactions and significant accumulation of tritium in material. Understanding the multifaceted physics of hydrogen retention in PFC is thus crucial, but remains challenging due to the wide spectrum of retention processes on PFC surface (erosion, co- deposition, etc.) and in PFC bulk (trap sites, bubbles, etc.) induced by long-time exposure of PFC to high flux of energy and particles. In this context, we revisit in this work some aspects of the reaction-diffusion models used to describe retention of hydrogen implanted in material in fusion relevant. We first focus on the analysis of thermal desorption spectroscopy (TDS) experiments, showing that the evolution of hydrogen concentration in material during TDS experiments is usually quasi-static. An analytic description of thermal desorption spectra (TDSP) is then obtained in quasi-static regime and is used to highlight dependencies of TDSP on hydrogen retention parameters. The interpretation of Arrhenius plots to characterize hydrogen retention processes is then revisited. Moreover, it is shown that retention processes can be characterized using the shape of desorption peaks in TDSP, and that long desorption tails in TDSP can be used to estimate activation energy of diffusion of hydrogen in PFC. Hydrogen retention induced by a large number of different types of traps is examined next. A reaction-diffusion model of TDSP with a large number of types of traps is presented for the first time. The application of this model is illustrated on several experimental TDSP available in literature, which are consistently reproduced using several types of traps with a unique broad spectrum of detrapping energies. The values of these detrapping energies are shown to be in agreement with values predicted by density functional theory simulations when several hydrogen atoms are trapped in one material vacancy. Effects of surface processes on hydrogen retention and recycling are investigated in the second part. First, long-term outgassing of hydrogen from PFC during off-plasma events is considered. The super- diffusive power-law decay in time of the hydrogen outgassing flux is modeled with a revisited single trap reaction-diffusion model, showing that hydrogen outgassing is either surface-limited or diffusion-limited. The outgassing regime is shown to be governed either by processes in the bulk or on the surface of material. The influence of hydrogen concentration profiles in material on the power-law exponents is analyzed as well. Finally, the different models proposed in the literature to describe power-law decays of hydrogen outgassing flux experimentally observed during off-plasma events are reconciled. Hydrogen recombination and desorption on tungsten surface is investigated next using molecular dynamics (MD) and accelerated molecular dynamics simulations. Adsorption states, diffusion, hydrogen recombination into molecules, and clustering of hydrogen on tungsten surfaces are analyzed. It is shown that tungsten hydrogen interatomic potential, available in literature and used in MD simulations, cannot reproduce main features of hydrogen molecular recombination on tungsten surface. Hydrogen clustering on tungsten surface is nevertheless observed during MD simulations. Effects of hydrogen clustering on hydrogen desorption are thus analyzed by introducing a kinetic model describing the competition between surface diffusion, clustering and recombination. Different desorption regimes are identified, which reproduce some aspects of desorption regimes experimentally observed when tungsten surface is saturated with hydrogen}, +@article{siccinio_feasibility_2021, + title = {Feasibility of {D}-{D} start-up under realistic technological assumptions for {EU}-{DEMO}}, + volume = {171}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621003306}, + doi = {10.1016/j.fusengdes.2021.112554}, + abstract = {One of the main issues in view of the realization of a DEMOnstration fusion reactor is the availability of a sufficient external supply of tritium (T) to start operation. T is an unstable nuclide, which is almost absent in nature and is currently available as by-product in e.g. CANDU, whose operation in the next decades (both in terms of life extension of existing reactors and construction of new ones) is at the moment under debate. During DEMO operation, T will be generated on-site by breeding blanket, employing the neutrons originating from D-T reaction. However, it is considered that a certain initial amount of T is needed to start operation, the so-called start-up inventory. An alternative approach consists of obtaining the start-up inventory exploiting reactions occurring in a D-D plasma, which generate T both directly in the plasma and via breeding in the breeding blanket. In the present paper, the conditions under which D-D start-up becomes a favorable option for a power plant are discussed. The analysis mainly focuses on the EU-DEMO reactor concept, for which design data are sufficient for a fairly quantitative evaluation of the relevant parameters. It is found that the unavoidable presence of elements requiring saturation before they are able to release significant amounts of T clamps the T production rate to the same order of magnitude as D-D reaction rate. Thus, under very optimistic assumptions, several hundreds of full-current D-D discharges are necessary for T to be available for plasma fueling, but more realistic estimates let this number raise up to several thousands.}, language = {en}, - school = {UC San Diego}, - author = {Guterl, Jérom̂e}, - year = {2015}, - keywords = {Macroscopic rate equations, Molecular Dynamics}, - file = {Guterl - 2015 - Modeling of hydrogen isotopes retention in plasma-.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\AIX848SE\\Guterl - 2015 - Modeling of hydrogen isotopes retention in plasma-.pdf:application/pdf}, + urldate = {2021-04-19}, + journal = {Fusion Engineering and Design}, + author = {Siccinio, M. and Chiovaro, P. and Cismondi, F. and Coleman, M. and Day, C. and Fable, E. and Federici, G. and Härtl, T. and Schwenzer, J. and Spagnuolo, G. A.}, + month = oct, + year = {2021}, + keywords = {EU-DEMO, Tritium, DD-start-up, Fuel cycle}, + pages = {112554}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EKUZB92B\\Siccinio et al. - 2021 - Feasibility of D-D start-up under realistic techno.pdf:application/pdf}, } -@article{dethloff_modeling_2012, - title = {Modeling of helium bubble nucleation and growth in neutron irradiated boron doped {RAFM} steels}, - volume = {426}, +@article{raiman_facility_2014, + title = {A facility for studying irradiation accelerated corrosion in high temperature water}, + volume = {451}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311511010695}, - doi = {10.1016/j.jnucmat.2011.12.025}, - abstract = {Reduced activation ferritic/martensitic (RAFM) steels are promising candidates for structural materials in future fusion technology. In addition to other irradiation defects, the transmuted helium is believed to strongly influence material hardening and embrittlement behavior. A phenomenological model based on kinetic rate equations is developed to describe homogeneous nucleation and growth of helium bubbles in neutron irradiated RAFM steels. The model is adapted to different 10B doped EUROFER97 based heats, which already had been studied in past irradiation experiments. Simulations yield bubble size distributions, whereby effects of helium generation rate, surface energy, helium sinks and helium density are investigated. Peak bubble diameters under different conditions are compared to preliminary microstructural results on irradiated specimens. Helium induced hardening was calculated by applying the Dispersed Barrier Hardening model to simulated cluster size distributions. Quantitative microstructural investigations of unirradiated and irradiated specimens will be used to support and verify the model.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311514001317}, + doi = {10.1016/j.jnucmat.2014.03.022}, + abstract = {A facility for the study of irradiation accelerated corrosion in high temperature water using in situ proton irradiation has been developed and validated. A specially designed beamline and flowing-water corrosion cell added to the 1.7MV tandem accelerator at the Michigan Ion Beam Laboratory provide the capability to study the simultaneous effects of displacement damage and radiolysis on corrosion. A thin sample serves as both a “window” into the corrosion cell through which the proton beam passes completely, and the sample for assessing irradiation accelerated corrosion. The facility was tested by irradiating stainless steel samples at beam current densities between 0.5 and 10μA/cm2 in 130°C and 320°C deaerated water, and 320°C water with 3wppm H2. Increases in the conductivity and dissolved oxygen content of the water varied with the proton beam current, suggesting that proton irradiation was accelerating the corrosion of the sample. Conductivity increases were greatest at 320°C, while DO increases were highest at 130°C. The addition of 3wppm H2 suppressed DO below detectable levels. The facility will enable future studies into the effect of irradiation on corrosion in high temperature water with in situ proton irradiation.}, language = {en}, number = {1}, - urldate = {2019-10-31}, + urldate = {2021-04-17}, journal = {Journal of Nuclear Materials}, - author = {Dethloff, Christian and Gaganidze, Ermile and Svetukhin, Vyacheslav V. and Aktaa, Jarir}, - month = jul, - year = {2012}, - keywords = {Bubble, Cluster dynamics}, - pages = {287--297}, - file = {Dethloff et al. - 2012 - Modeling of helium bubble nucleation and growth in.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D9Q4DBZX\\Dethloff et al. - 2012 - Modeling of helium bubble nucleation and growth in.pdf:application/pdf}, + author = {Raiman, Stephen S. and Flick, Alexander and Toader, Ovidiu and Wang, Peng and Samad, Nassim A. and Jiao, Zhijie and Was, Gary S.}, + month = aug, + year = {2014}, + pages = {40--47}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\963I7BH7\\S0022311514001317.html:text/html}, } -@article{shimwell_multiphysics_2019, - title = {Multiphysics analysis with {CAD}-based parametric breeding blanket creation for rapid design iteration}, - volume = {59}, - copyright = {All rights reserved}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab0016}, - doi = {10.1088/1741-4326/ab0016}, - abstract = {Breeding blankets are designed to ensure tritium self-sufficiency in deuterium–tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. Blanket design is critical to the success of fusion reactors and integral to the design process. Neutronic simulations of breeder blankets are regularly performed to ascertain the performance of a particular design. An iterative process of design improvements and parametric studies are required to optimize the design and meet performance targets. Within the EU DEMO program the breeding blanket design cycle is repeated for each new baseline design. One of the key steps is to create three-dimensional models suitable primarily for use in neutronics, but could be used in other computer-aided design (CAD)-based physics and engineering analyses. This article presents a novel blanket design tool which automates the process of producing heterogeneous 3D CAD-based geometries of the helium-cooled pebble bed, water-cooled lithium lead, helium-cooled lithium lead and dual-coolant lithium lead blanket types. The paper shows a method of integrating neutronics, thermal analysis and mechanical analysis with parametric CAD to facilitate the design process. The blanket design tool described in this paper provides parametric geometry for use in neutronics and engineering simulations. This paper explains the methodology of the design tool and demonstrates use of the design tool by generating all four EU blanket designs using the EU DEMO baseline. Neutronics and heat transfer simulations using the models have been carried out. The approach described has the potential to considerably speed up the design cycle and greatly facilitate the integration of multiphysics studies.}, +@article{olson_materials_2009, + series = {Fluorine \& {Nuclear} {Energy}}, + title = {Materials corrosion in molten {LiF}–{NaF}–{KF} salt}, + volume = {130}, + issn = {0022-1139}, + url = {https://www.sciencedirect.com/science/article/pii/S002211390800119X}, + doi = {10.1016/j.jfluchem.2008.05.008}, + abstract = {Corrosion tests of high temperature alloys, Hastelloy-N, Hastelloy-X, Haynes-230, Inconel-617, and Incoloy-800H were performed in molten fluoride salt, FLiNaK (LiF–NaF–KF:46.5–11.5–42mol\%) with the goal of understanding the corrosion mechanisms and ranking these alloys for their suitability for molten fluoride salt heat exchanger and thermal storage applications. The tests were performed at 850°C for 500h in sealed graphite crucibles under an argon cover gas. Corrosion was noted to occur predominantly by dealloying of Cr from the alloys, an effect that was particularly pronounced at the grain boundaries of these alloys. Weight-loss due to corrosion generally correlated with the initial Cr-content of the alloys, and was consistent with the Cr-content measured in the salts after corrosion tests. Two Cr-free alloys, Ni-201 and Nb–1Zr, were also tested. Ni-201, a nearly pure Ni alloy with minor alloying additions, exhibited good resistance to corrosion, whereas Nb–1Zr alloy exhibited extensive corrosion attack. The graphite crucible may have accelerated the corrosion process by promoting the formation of carbide phases on the walls of the test crucibles, but did not alter the basic corrosion mechanism.}, language = {en}, - number = {4}, - journal = {Nuclear Fusion}, - author = {Shimwell, Jonathan and Delaporte-Mathurin, Rémi and Jaboulay, Jean-Charles and Aubert, Julien and Richardson, Chris and Bowman, Chris and Davis, Andrew and Lahiff, Andrew and Bernardi, James and Yasin, Sikander and Tang, Xiaoying}, - month = mar, - year = {2019}, - pages = {046019}, - file = {Shimwell et al. - 2019 - Multiphysics analysis with CAD-based parametric br.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PSZ49KMV\\Shimwell et al. - 2019 - Multiphysics analysis with CAD-based parametric br.pdf:application/pdf}, + number = {1}, + urldate = {2021-04-16}, + journal = {Journal of Fluorine Chemistry}, + author = {Olson, Luke C. and Ambrosek, James W. and Sridharan, Kumar and Anderson, Mark H. and Allen, Todd R.}, + month = jan, + year = {2009}, + keywords = {Corrosion, Molten salt, Materials, FLiNaK, Fluorides}, + pages = {67--73}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\QFJPC5YY\\Olson et al. - 2009 - Materials corrosion in molten LiF–NaF–KF salt.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\H243BZZA\\S002211390800119X.html:text/html}, } -@article{frauenfelder_solution_1969, - title = {Solution and {Diffusion} of {Hydrogen} in {Tungsten}}, - volume = {6}, - issn = {0022-5355}, - url = {https://avs.scitation.org/doi/10.1116/1.1492699}, - doi = {10.1116/1.1492699}, - number = {3}, - urldate = {2019-10-07}, - journal = {Journal of Vacuum Science and Technology}, - author = {Frauenfelder, R.}, +@article{zheng_corrosion-induced_2016, + title = {Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten {Li2BeF4}({FLiBe}) salt}, + volume = {482}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311516309138}, + doi = {10.1016/j.jnucmat.2016.10.023}, + abstract = {The microstructural developments in the near-surface regions of AISI 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) salt have been investigated with the goal of using this material for the construction of the fluoride salt-cooled high-temperature reactor (FHR), a leading nuclear reactor concept for the next generation nuclear plants (NGNP). Tests were conducted in molten FLiBe salt (melting point: 459 °C) at 700 °C in graphite crucibles and 316 stainless steel crucibles for exposure duration of up to 3000 h. Corrosion-induced microstructural changes in the near-surface regions of the samples were characterized using scanning electron microscopy (SEM) in conjunction with energy dispersive x-ray spectroscopy (EDS) and electron backscatter diffraction (EBSD), and scanning transmission electron microscopy (STEM) with EDS capabilities. Intergranular corrosion attack in the near-surface regions was observed with associated Cr depletion along the grain boundaries. High-angle grain boundaries (15–180°) were particularly prone to intergranular attack and Cr depletion. The depth of attack extended to the depths of 22 μm after 3000-h exposure for the samples tested in graphite crucible, while similar exposure in 316 stainless steel crucible led to the attack depths of only about 11 μm. Testing in graphite crucibles led to the formation of nanometer-scale Mo2C, Cr7C3 and Al4C3 particle phases in the near-surface regions of the material. The copious depletion of Cr in the near-surface regions induced a γ-martensite to α-ferrite phase (FeNix) transformation. Based on the microstructural analysis, a thermal diffusion controlled corrosion model was developed and experimentally validated for predicting long-term corrosion attack depth.}, + language = {en}, + urldate = {2021-04-16}, + journal = {Journal of Nuclear Materials}, + author = {Zheng, Guiqiu and He, Lingfeng and Carpenter, David and Sridharan, Kumar}, + month = dec, + year = {2016}, + keywords = {Corrosion, Molten salt, 316 stainless steel, Microstructure, Nuclear reactor}, + pages = {147--155}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\GH3UXQSJ\\Zheng et al. - 2016 - Corrosion-induced microstructural developments in .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\8KAF5DBG\\S0022311516309138.html:text/html}, +} + +@techreport{devan_corrosion_1962, + title = {{CORROSION} {BEHAVIOR} {OF} {REACTOR} {MATERIALS} {IN} {FLUORIDE} {SALT} {MIXTURES}}, + url = {https://www.osti.gov/biblio/4774669}, + abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information}, + language = {English}, + number = {ORNL-TM-328}, + urldate = {2021-04-16}, + institution = {Oak Ridge National Lab., Tenn.}, + author = {DeVan, J. H. and Evans, I. I. I.}, + month = sep, + year = {1962}, + doi = {10.2172/4774669}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4XUW6QLP\\DeVan et Evans - 1962 - CORROSION BEHAVIOR OF REACTOR MATERIALS IN FLUORID.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PZHJDYGL\\4774669.html:text/html;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ATGWQ2H8\\4774669.html:text/html}, +} + +@book{young_high_2016, + title = {High {Temperature} {Oxidation} and {Corrosion} of {Metals}}, + isbn = {978-0-08-100119-6}, + abstract = {High Temperature Oxidation and Corrosion of Metals, Second Edition, provides a high level understanding of the fundamental mechanisms of high temperature alloy oxidation. It uses this understanding to develop methods of predicting oxidation rates and the way they change with temperature, gas chemistry, and alloy composition. The book focuses on the design and selection of alloy compositions which provide optimal resistance to attack by corrosive gases, providing a rigorous treatment of the thermodynamics and kinetics underlying high temperature alloy corrosion. In addition, it emphasizes quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities, and alloy compositions. Users will find this book to be an indispensable source of information for researchers and students who are dealing with high temperature corrosion.Emphasizes quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities, and alloy compositionsUses phase diagrams and diffusion paths to analyze and interpret scale structures and internal precipitation distributionsPresents a detailed examination of corrosion in industrial gases (water vapor effects, carburization and metal dusting, sulphidation)Contains numerous micrographs, phase diagrams, and tabulations of relevant thermodynamic and kinetic data Combines physical chemistry and materials science methodologiesProvides two completely new chapters (chapters 11 and 13), and numerous other updates throughout the text}, + language = {en}, + publisher = {Elsevier}, + author = {Young, David John}, month = may, - year = {1969}, - keywords = {Experiment}, - pages = {388--397}, -} - -@article{anderl_deuterium_1999, - title = {Deuterium transport in {Cu}, {CuCrZr}, and {Cu}/{Be}}, - volume = {266-269}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311598008782}, - doi = {10.1016/S0022-3115(98)00878-2}, - abstract = {This paper presents the results of deuterium implantation/permeation experiments and TMAP4 simulations for a CuCrZr alloy, for OFHC-Cu and for a Cu/Be bi-layered structure at temperatures from 700 to 800 K. Experiments used a mass-analyzed, 3-keV D3+ ion beam with particle flux densities of 5×1019 to 7×1019 D/m2 s. Effective diffusivities and surface molecular recombination coefficients were derived giving Arrhenius pre-exponentials and activation energies for each material: CuCrZr alloy, (2.0×10−2 m2/s, 1.2 eV) for diffusivity and (2.9×x10−14 m4/s, 1.92 eV) for surface molecular recombination coefficients; OFHC Cu, (2.1×10−6 m2/s, 0.52 eV) for diffusivity and (9.1×10−18 m4/s, 0.99 eV) for surface molecular recombination coefficients. TMAP4 simulation of permeation data measured for a Cu/Be bi-layer sample was achieved using a four-layer structure (Cu/BeO interface/Be/BeO back surface) and recommended values for diffusivity and solubility in Be, BeO and Cu.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Anderl, R. A. and Hankins, M. R. and Longhurst, G. R. and Pawelko, R. J.}, - month = mar, - year = {1999}, - keywords = {Experiment}, - pages = {761--765}, - file = {Anderl et al. - 1999 - Deuterium transport in Cu, CuCrZr, and CuBe.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WXFLBVUE\\Anderl et al. - 1999 - Deuterium transport in Cu, CuCrZr, and CuBe.pdf:application/pdf}, + year = {2016}, + note = {Google-Books-ID: TVXBBwAAQBAJ}, + keywords = {Science / Chemistry / Physical \& Theoretical, Technology \& Engineering / Materials Science / General, Technology \& Engineering / Metallurgy}, } -@article{causey_hydrogen_2002, - title = {Hydrogen isotope retention and recycling in fusion reactor plasma-facing components}, - volume = {300}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311501007322}, - doi = {10.1016/S0022-3115(01)00732-2}, - abstract = {The proper design of a fusion reactor is not possible unless there is an understanding of the hydrogen isotope retention and recycling for the plasma-facing components. From the tritium inventory point of view, it is absolutely necessary to understand the short-term and long-term hydrogen isotopes retention characteristics of the individual materials used for the first wall and divertor. From the plasma density and fueling point of view, it is necessary to understand the recycling characteristics of these materials. This report is an overview of the available data on hydrogen isotope retention and recycling for beryllium, tungsten, carbon, and selected liquid metals. For each material discussed, recommendations are made as to the most appropriate values to use for parameters such as diffusivity, solubility, recombination rate coefficient, and trapping.}, - number = {2}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Causey, Rion A}, - month = feb, - year = {2002}, - keywords = {Experiment}, - pages = {91--117}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Y4ZM8B4Y\\Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8KN2HJM4\\S0022311501007322.html:text/html;Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BVB4EWBA\\Causey - 2002 - Hydrogen isotope retention and recycling in fusion.pdf:application/pdf}, +@article{sorbom_liquid_2012, + title = {Liquid immersion blanket design for use in a compact modular fusion reactor}, + url = {http://adsabs.harvard.edu/abs/2012APS..DPPUP8055S}, + abstract = {Traditional tritium breeding blankets in fusion reactor designs include a large amount of structural material. This results in complex +engineering requirements, complicated sector maintenance, and marginal tritium breeding ratios (TBR). We present a conceptual design of a fully liquid blanket. To maximize tritium breeding volume, the vacuum vessel is completely immersed in a continuously recycled FLiBe blanket, with the exception of small support posts. FLiBe has a wide liquid +temperature window (459 C to 1430 C), low electrical conductivity to minimize MHD effects, similar thermal/fluid characteristics to water, and is chemically inert. While tritium breeding with FLiBe in +traditional blankets is poor, we use MCNP neutronics analysis to show that the immersion blanket design coupled with a beryllium neutron multiplier results in TBR {\textgreater} 1. FLiBe is shown to be a sufficient radiation shield for the toroidal field magnets and can be used as a coolant for the vacuum vessel and divertor, allowing for a simplified single-phase, low-pressure, single-fluid cooling scheme. When coupled with a high-field compact reactor design, the immersion blanket +eliminates the need for complex sector maintenance, allows the vacuum vessel to be a replaceable component, and reduces financial cost.}, + urldate = {2021-04-16}, + author = {Sorbom, Brandon and Ball, Justin and Barnard, Harold and Haakonsen, Christian and Hartwig, Zachary and Olynyk, Geoffrey and Sierchio, Jennifer and Whyte, Dennis}, + month = oct, + year = {2012}, + note = {Conference Name: APS Meeting Abstracts}, + pages = {UP8.055}, } -@article{tsukatani_deuterium_2011, - title = {Deuterium {Retention} in {Damaged} {Tungsten}}, - volume = {60}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST11-A12727}, - doi = {10.13182/FST11-A12727}, - abstract = {In this research, thermal desorption characteristics of deuterium retained at trap sites of W created by irradiation of 300 keV hydrogen ions have been studied. With 10 hours of annealing, about 85\% of deuterium was desorbed at temperatures of 300 °C and 350 °C, while deuterium desorption at 250 °C was about 60\%. To estimate trapping energy of trap sites in this damaged W, TMAP simulation was performed. The result shows that the trapping energy of 1.29eV well accounted for the result of 250 °C annealing. In view that in the literature the vacancy trapping energy of hydrogen in tungsten was estimated to be close to 1.43 eV and the sensitivity analysis has given an uncertainty for the trapping energy of the order of 0.1 eV, it appears that the dominant trapping site type in the investigated damaged tungsten consists of vacancies.}, - number = {4}, - urldate = {2019-10-07}, - journal = {Fusion Science and Technology}, - author = {Tsukatani, K. and Ueda, Y. and Tanimoto, K. and Lee, H. T. and Ohtsuka, Y. and Taniguchi, M. and Inoue, T. and Sakamoto, K. and Takagi, I. and Yoshida, N.}, +@article{sorbom_arc_2015, + title = {{ARC}: {A} compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets}, + volume = {100}, + issn = {0920-3796}, + shorttitle = {{ARC}}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379615302337}, + doi = {10.1016/j.fusengdes.2015.07.008}, + abstract = {The affordable, robust, compact (ARC) reactor is the product of a conceptual design study aimed at reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ∼200–250MWe tokamak reactor with a major radius of 3.3m, a minor radius of 1.1m, and an on-axis magnetic field of 9.2T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This allows the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Qp≈13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ∼63\%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ∼23T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25MW of lower hybrid and 13.6MW of ion cyclotron fast wave power. The resulting efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio≥1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.}, + language = {en}, + urldate = {2021-04-16}, + journal = {Fusion Engineering and Design}, + author = {Sorbom, B. N. and Ball, J. and Palmer, T. R. and Mangiarotti, F. J. and Sierchio, J. M. and Bonoli, P. and Kasten, C. and Sutherland, D. A. and Barnard, H. S. and Haakonsen, C. B. and Goh, J. and Sung, C. and Whyte, D. G.}, month = nov, - year = {2011}, - keywords = {Experiment}, - pages = {1543--1547}, + year = {2015}, + keywords = {Fusion nuclear science facility, Tokamak, Compact pilot reactor, High magnetic field, High-field launch, Liquid immersion blanket, Superconducting joints}, + pages = {378--405}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ID5WW77S\\Sorbom et al. - 2015 - ARC A compact, high-field, fusion nuclear science.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CDC5ZJ83\\S0920379615302337.html:text/html}, } -@article{anderl_deuterium_1992, - title = {Deuterium {Transport} and {Trapping} in {Polycrystalline} {Tungsten}}, - volume = {21}, - issn = {0748-1896}, - url = {https://doi.org/10.13182/FST92-A29837}, - doi = {10.13182/FST92-A29837}, - abstract = {Deuterium permeation studies for polycrystalline tungsten foil have been conducted to provide data for estimating tritium transport and trapping in tungsten-clad divertors proposed for advanced fusion-reactor concepts. Based on a detailed transmission electron microscopy (TEM) microstructural characterization of the specimen material and on analyses of permeation data measured at temperatures ranging from 610 to 823 K for unannealed and annealed tungsten foil (25 µm thick), we note the following key results: (1) deuterium transport in tungsten foil is dominated by extensive trapping that varies inversely with prior anneal temperatures of the foil material, (2) the reduction in the trapped fraction correlates with a corresponding elimination of a high density of dislocations in cell-wall structures introduced during the foil fabrication process, (3) trapping behavior in these foils can be modelled using trap energies between 1.3 eV and 1.5 eV and trap densities ranging from 1 × 10−5 to 7 × 10−5 atom fraction.}, - number = {2P2}, - urldate = {2019-10-07}, - journal = {Fusion Technology}, - author = {Anderl, R. A. and Holland, D. F. and Longhurst, G. R. and Pawelko, R. J. and Trybus, C. L. and Sellers, C. H.}, - month = mar, - year = {1992}, - keywords = {Experiment}, - pages = {745--752}, +@article{tassone_computational_2021, + title = {Computational {MHD} analyses in support of the design of the {WCLL} {TBM} breeding zone}, + volume = {170}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621003112}, + doi = {10.1016/j.fusengdes.2021.112535}, + abstract = {The Water-Cooled Lithium Lead (WCLL) is a blanket concept pursued in the framework of Test Blanket Module (TBM) campaign in ITER. Even if the liquid metal is circulated slowly in the component, magnetohydrodynamic (MHD) pressure losses are still expected to be significant. The aim of this paper is to assess the MHD pressure losses in the TBM frontal part, also called Breeding Zone (BZ). There, important contributions are caused by the manifold interface, the presence of cooling pipes obstructing the fluid movement, a sharp hairpin bend, and non-uniform wall thickness of the walls. Direct numerical simulation of 2D and 3D MHD flows is used to estimate the head loss for each one of these elements. A scaling law is derived to allow quick estimate of the pressure loss from reference parameters. The main contribution to the head loss is caused by the windows that connect the BZ with the manifold.}, + language = {en}, + urldate = {2021-04-06}, + journal = {Fusion Engineering and Design}, + author = {Tassone, Alessandro and Caruso, Gianfranco}, + month = sep, + year = {2021}, + keywords = {ITER, Liquid metals, TBM, Magnetohydrodynamics (MHD), Pressure drop, WCLL blanket}, + pages = {112535}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ZK4SLJ89\\Tassone et Caruso - 2021 - Computational MHD analyses in support of the desig.pdf:application/pdf}, } -@article{poon_flux_2002, - title = {Flux dependence of deuterium retention in single crystal tungsten}, - volume = {307-311}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311502009467}, - doi = {10.1016/S0022-3115(02)00946-7}, - abstract = {The retention of deuterium in single crystal tungsten has been measured as a function of the incident ion flux in the range of 1×1017–5×1019 D+/m2s at 300 K. Incident D3+ ions were implanted to fluences of 1021, 1022, and 1023 D+/m2 with ion energies (500 eV/D+) below the threshold energy for elastic collision damage. Above 3×1018 D+/m2s, little or no flux dependence is seen. However, a rapid decrease in retention is seen for incident fluxes below 1018 D+/m2s at the 1021 D+/m2 fluence, suggesting a threshold value below which retention is strongly reduced. Flux dependence at the higher fluences show a smaller decrease in retention with decreasing flux. The observed results are consistent with trapping and trap evolution by cluster and cavity formation. The effect of specimen surface preparation has proved to be very significant, especially for the lower fluence.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Poon, M. and Macaulay-Newcombe, R. G. and Davis, J. W. and Haasz, A. A.}, - month = dec, - year = {2002}, - keywords = {Experiment}, - pages = {723--728}, - file = {Poon et al. - 2002 - Flux dependence of deuterium retention in single c.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HF5GTHK7\\Poon et al. - 2002 - Flux dependence of deuterium retention in single c.pdf:application/pdf}, +@article{utili_development_2021, + title = {Development of anti-permeation and corrosion barrier coatings for the {WCLL} breeding blanket of the {European} {DEMO}}, + volume = {170}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621002295}, + doi = {10.1016/j.fusengdes.2021.112453}, + abstract = {Tritium permeation from breeder material to the Water Coolant System (WCS) in Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the technological issues to be solved in the design of the European DEMO. Since the tritium extraction from the Water Coolant System is more challenging and expensive than the extraction from the eutectic alloy PbLi, it is mandatory to use of a protective coating on the blanket wall to minimize the permeation rate. Moreover, a protective coating can prevent the corrosion of EUROFER steel by the action of PbLi. alumina-based coatings are considered as reference for barriers thanks to their good chemical compatibility with the PbLi alloy and their capability to reduce permeation. Three coating technologies were selected in the frame of the EUROfusion project: electrochemical ECX (chemical deposition) process, Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) coating. The coatings were developed and optimized in order to satisfy the design requirements of good mechanical compatibility with steels, strong adhesion, corrosion compatibility in PbLi at relevant BB design conditions and a Permeation Reduction Factor at least of 200 under neutron irradiation. The present paper aims to describe the status of the technologies and the main results obtained. The final objectives of the R\&D activities are to demonstrate the applicability of the coating to WCLL BB and therefore the scale-up of the technologies from laboratory scale to the BB scale.}, + language = {en}, + urldate = {2021-04-03}, + journal = {Fusion Engineering and Design}, + author = {Utili, Marco and Bassini, Serena and Cataldo, Sebastiano and Di Fonzo, Fabio and Kordac, Michal and Hernandez, Teresa and Kunzova, Klara and Lorenz, Julia and Martelli, Daniele and Padino, Boris and Moroño, Alejandro and Tarantino, Mariano and Schroer, Carsten and Spagnuolo, Gandolfo Alessandro and Vala, Ladislav and Vanazzi, Matteo and Venturini, Alessandro}, + month = sep, + year = {2021}, + keywords = {DEMO, Corrosion, Irradiation, Tritium permeation, Alumina coating, PbLi}, + pages = {112453}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DG4E4YVN\\Utili et al. - 2021 - Development of anti-permeation and corrosion barri.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GBKYI6VX\\S0920379621002295.html:text/html}, } -@article{condon_hydrogen_1993, - title = {Hydrogen bubbles in metals}, - volume = {207}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/002231159390244S}, - doi = {10.1016/0022-3115(93)90244-S}, - abstract = {First a brief introduction to hydrogen bubbles in metals and their technological importance is presented. The review concentrates on those areas of bubble formation where the distinct chemical character of hydrogen is important. A distinction is made between nucleation and subsequent cavity growth mechanisms. Both homogeneous and heterogenous nucleation are given as possibilities. Three cavity growth mechanisms are delineated: plastic deformation near a surface referred to as “blistering”, plastic deformation by loop punching, and the collection of vacancy-hydrogen complexes. Several factors are considered which can determine the particular mechanism which applies, such as the source of the hydrogen and its concentration, solubility and diffusivity and the concentration of defects in the metal. A preemptive reaction to bubble formation is the one leading to metal hydride formation. This reaction must be considered both for predicting the formation of bubbles and for experimental observations. The possibility of plastic deformation near a free surface can lead to blistering, and this must be considered. The current understanding of loop punching processes is presented and applied to hydrogen bubble formation. Vacancy clustering may also lead to void formation which may then absorb further hydrogen-vacancy complexes. Illustrative examples of hydrogen filled cavities in selected metals and alloys are discussed in detail.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Condon, J. B. and Schober, T.}, - month = dec, - year = {1993}, - keywords = {Experiment}, - pages = {1--24}, - file = {Condon et Schober - 1993 - Hydrogen bubbles in metals.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7XTBMM2I\\Condon et Schober - 1993 - Hydrogen bubbles in metals.pdf:application/pdf}, +@article{goldstein_diffusion_2007, + title = {Diffusion {Limited} {Reactions}}, + volume = {67}, + issn = {0036-1399}, + url = {https://www.jstor.org/stable/40233434}, + abstract = {Changes to the relative separation of molecules or other interacting species on account of diffusion accompany their associative or dissociative reaction. The molecules are symbolized, for two distinct types, A,B, by the relations A+B =AB, and, if [A], [B], and [AB] denote the corresponding densities, the equation {\textless}tex-math{\textgreater}\$\{d {\textbackslash}over \{dt\}\}[AB] = K\_ + [A][B]\${\textless}/tex-math{\textgreater} specifies an associative process with forward rate constant k₊. An approximate version of the preceding takes the form of a linear differential equation, which can be employed to obtain significant estimates for both k₊ and the flux function d[AB]/dt. Such estimates are presented in different circumstances, including the localization of A,B on a common planar surface or their distribution in space, and also when the domain of A is a half space whereas that of B is a bounding planar surface. It proves advantageous to reformulate the last, a mixed boundary value problem, in terms of a linear integral equation. Biological applications are discussed, including the mechanism for the observed phosphorylation of proteins in resting cells and the incipience of phototransduction in rod photoreceptors.}, + number = {4}, + urldate = {2021-04-02}, + journal = {SIAM Journal on Applied Mathematics}, + author = {Goldstein, Byron and Levine, Harold and Torney, David}, + year = {2007}, + note = {Publisher: Society for Industrial and Applied Mathematics}, + pages = {1147--1165}, } -@article{yu_deuterium_2019, - title = {Deuterium retention in re-solidified tungsten and beryllium}, - volume = {18}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179118302436}, - doi = {10.1016/j.nme.2019.01.011}, - abstract = {Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads from edge localized modes (ELMs), and melting of the entire divertor surface will occur during vertical displacement events (VDEs) and disruptions. In addition, understanding tritium retention in plasma facing materials is critical for the successful operation of ITER due to safety reasons. Thus, the question of how melting affects hydrogenic retention is highly relevant for fusion devices. Here we use an Nd:YAG laser to melt tungsten and beryllium in vacuo, and the samples are subsequently exposed to deuterium plasma with sample temperatures ranging from 370 to 750 K. The deuterium content in re-solidified and reference (no laser) samples is measured using thermal desorption spectroscopy and modeled using TMAP-7. In all cases, the re-solidified samples have lower retention compared to the reference samples. For re-solidified tungsten, the most significant effect is in the 1.8 eV trap with peak thermal desorption temperature of ∼750 K, which had a 77\% reduction in the peak release rate compared with the reference sample. SEM imaging indicates that laser melting and re-solidification of tungsten anneals intrinsic defects that act as nucleation sites for larger-scale defects that develop during plasma exposure. However, melting does not significantly affect traps with lower de-trapping energies of 1.0 eV and 1.4 eV. In beryllium, melting and cracking results in lower retention compared to the reference sample by 40\%, and thermal desorption profiles indicate that the diffusion depth of deuterium into re-solidified beryllium is lower than that of the reference sample.}, - urldate = {2019-10-07}, - journal = {Nuclear Materials and Energy}, - author = {Yu, J. H. and Simmonds, M. J. and Baldwin, M. J. and Doerner, R. P.}, +@article{wang_thermal_2020, + title = {Thermal damage of tungsten-armored plasma-facing components under high heat flux loads}, + volume = {10}, + copyright = {2020 The Author(s)}, + issn = {2045-2322}, + url = {https://www.nature.com/articles/s41598-020-57852-8}, + doi = {10.1038/s41598-020-57852-8}, + abstract = {Fusion energy is expected as a promising candidate for alternative next generation energy. For fusion reactor, the plasma facing components (PFCs) are the most critical components to achieve this goal. PFCs will suffer severe thermal shock due to repective cyclic high heat flux (HHF) loads. This paper investigates the effects of thermal shock and damage behavior of tungsten armored PFCs under steady, transient and combined thermal loads. The distribution of stress field is analyzed, and crack initiation is predicted using the extended finite element method (XFEM). The unique features of thermal-mechanical behavior of tungsten armored PFCs under simulated service condition are discussed. The dominant factor of the cracking of the tungsten armor is the brittleness of tungsten below ductile-to-brittle transition temperature (DBTT). Under the steady loads, the cracking position is apt to near the interface of tungsten armor and the interlayer, and the threshold of cracking is between 14 MW/m2 and 16 MW/m2. With 6 MW/m2 steady loads, applying 1 ms duration of transient load, the cracking threshold is between 0.2 GW/m2 to 0.4 GW/m2. The depth of cracking increases from 100 um to 500 um with the transient load increasing from 0.4 GW/m2 to 1.0 GW/m2. Researches are useful for the design and structural optimization of tungsten-armored PFCs, and the long-term stable operation of further reactor.}, + language = {en}, + number = {1}, + urldate = {2021-04-01}, + journal = {Scientific Reports}, + author = {Wang, Shuming and Li, Jiangshan and Wang, Ye and Zhang, Xiaofang and Wang, Ruiping and Wang, Yanru and Cao, Jian}, month = jan, - year = {2019}, - keywords = {Experiment}, - pages = {297--306}, - file = {Yu et al. - 2019 - Deuterium retention in re-solidified tungsten and .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8ZNLFRN8\\Yu et al. - 2019 - Deuterium retention in re-solidified tungsten and .pdf:application/pdf}, + year = {2020}, + note = {Number: 1 +Publisher: Nature Publishing Group}, + pages = {1359}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\R9ZREUD2\\Wang et al. - 2020 - Thermal damage of tungsten-armored plasma-facing c.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NXVP5HK9\\s41598-020-57852-8.html:text/html}, } -@article{ogorodnikova_deuterium_2003, - series = {Plasma-{Surface} {Interactions} in {Controlled} {Fusion} {Devices} 15}, - title = {Deuterium retention in tungsten in dependence of the surface conditions}, - volume = {313-316}, +@article{thompson_measuring_2016, + title = {Measuring helium bubble diameter distributions in tungsten with grazing incidence small angle x-ray scattering ({GISAXS})}, + volume = {T167}, + issn = {0031-8949, 1402-4896}, + url = {https://iopscience.iop.org/article/10.1088/0031-8949/2016/T167/014014}, + doi = {10.1088/0031-8949/2016/T167/014014}, + abstract = {Grazing incidence small angle x-ray scattering was performed on tungsten samples exposed to helium plasma in the MAGPIE and Pisces-A linear plasma devices to measure the size distributions of resulting helium nano-bubbles. Nano-bubbles were fitted assuming spheroidal particles and an exponential diameter distribution. These particles had mean diameters between 0.36 and 0.62 nm. Pisces-A exposed samples showed more complex patterns, which may suggest the formation of faceted nano-bubbles or nano-scale surface structures.}, + language = {en}, + urldate = {2021-04-01}, + journal = {Physica Scripta}, + author = {Thompson, M and Kluth, P and Doerner, R P and Kirby, N and Riley, D and Corr, C S}, + month = feb, + year = {2016}, + pages = {014014}, + file = {Thompson et al. - 2016 - Measuring helium bubble diameter distributions in .pdf:D\:\\Logiciels\\data_zotero\\storage\\7D7FLYTE\\Thompson et al. - 2016 - Measuring helium bubble diameter distributions in .pdf:application/pdf}, +} + +@article{chen_deuterium_2021, + title = {Deuterium transport and retention properties of representative fusion blanket structural materials}, + volume = {549}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311502013752}, - doi = {10.1016/S0022-3115(02)01375-2}, - abstract = {The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter of the deuterium (D) retention database, new measurements of ion-driven D retention in polycrystalline W foil have been performed to clarify the mechanism of hydrogen isotope inventory in W. Deuterium retention has been investigated as a function of ion fluence, implantation temperature, incident energy and surface conditions. Special attention has been given on the investigation of D retention in thin films of tungsten carbide and tungsten oxide which can be formed on W surface in a fusion device. Such kinds of films increase the D retention in W. Several points are reviewed: (i) inventory in pure W, (ii) inventory in W pre-implanted by carbon ions and (iii) inventory in tungsten oxide.}, - urldate = {2019-10-07}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311521001288}, + doi = {10.1016/j.jnucmat.2021.152904}, + abstract = {Reduced activation ferritic-martensitic (RAFM) steels have been developed for decades for use as fusion blanket structural materials, and have advantages in both mechanical properties and irradiation resistance following careful engineering of the microstructure. However, the hydrogen isotope behavior in these proposed fusion structural materials is not well understood, but is important to assess since it impacts the fusion reactor safety and self-sufficient tritium fuel cycle. In this work, we investigated deuterium transport and retention in representative advanced RAFM steels, including castable nanostructured alloys (CNAs), and oxide-dispersion-strengthened (ODS) steels. A gas-driven permeation (GDP) system was used to measure the permeability, diffusivity and solubility of the studied materials, covering the temperature range from 623 K to 873 K, and the loading pressures from 1.8×104 to 1.0×105 Pa. The results indicated that the deuterium permeability has little material dependence. In contrast, the deuterium diffusivity of the studied materials showed significant variation. The deuterium diffusivity in ODS steels is one order of magnitude lower than that in RAFM steels and CNAs, and correspondingly, have an effective solubility that is 2–10 times larger than RAFM steels and CNAs. In addition, thermal desorption spectroscopy (TDS) measurements were performed to assess the deuterium retention and desorption of these materials following a static thermal deuterium charging at 723 Kfor 1 hour under the deuterium pressure of 1.0×105Pa. It was found that ODS steels exhibit the highest deuterium retention and have broader desorption peaks. Microstructural features contributing to deuterium retention and impacting deuterium transport are discussed to rationalize the observed deuterium behavior in the studied RAFM steels.}, + language = {en}, + urldate = {2021-03-31}, journal = {Journal of Nuclear Materials}, - author = {Ogorodnikova, O. V and Roth, J and Mayer, M}, - month = mar, - year = {2003}, - keywords = {Experiment}, - pages = {469--477}, - file = {Ogorodnikova et al. - 2003 - Deuterium retention in tungsten in dependence of t.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LMRENIS9\\Ogorodnikova et al. - 2003 - Deuterium retention in tungsten in dependence of t.pdf:application/pdf}, + author = {Chen, Ze and Hu, Xunxiang and Ye, Minyou and Wirth, Brian D.}, + month = jun, + year = {2021}, + keywords = {Deuterium retention, Deuterium transport, Reduced activation ferritic-martensitic steels}, + pages = {152904}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YSJHYIX3\\Chen et al. - 2021 - Deuterium transport and retention properties of re.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\G8R2BGGL\\S0022311521001288.html:text/html}, } -@article{yajima_kinetics_2019, - title = {Kinetics of deuterium penetration into neutron-irradiated tungsten under exposure to high flux deuterium plasma}, - volume = {21}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179118300516}, - doi = {10.1016/j.nme.2019.100699}, - abstract = {The objective of this study is to investigate the effects of neutron (n) irradiation on hydrogen isotope transport in tungsten (W). W samples were irradiated with neutrons in a fission reactor and then exposed to high flux deuterium (D) plasma at 563 K in a linear plasma device. The fraction of D release increased with increasing exposure time. In addition, the D retention in n-irradiated W increased in proportion to the square root of the plasma exposure time. These observations were explained by increase in the penetration depth of D with filling up displacement damages acting as strong trapping sites.}, +@article{valles_temperature_2017, + title = {Temperature dependence of underdense nanostructure formation in tungsten under helium irradiation}, + volume = {490}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311516312478}, + doi = {10.1016/j.jnucmat.2017.04.021}, + abstract = {Recently, tungsten has been found to form a highly underdense nanostructured morphology (“W fuzz”) when bombarded by an intense flux of He ions, but only in the temperature window 900–2000 K. Using object kinetic Monte Carlo simulations (pseudo-3D simulations) parameterized from first principles, we show that this temperature dependence can be understood based on He and point defect clustering, cluster growth, and detrapping reactions. At low temperatures ({\textless}900 K), fuzz does not grow because almost all He is trapped in very small He-vacancy clusters. At high temperatures ({\textgreater}2300 K), all He is detrapped from clusters, preventing the formation of the large clusters that lead to fuzz growth in the intermediate temperature range.}, language = {en}, - urldate = {2019-11-05}, - journal = {Nuclear Materials and Energy}, - author = {Yajima, M. and Hatano, Y. and Ohno, N. and Kuwabara, T. and Toyama, T. and Takagi, M. and Suzuki, K.}, - month = dec, - year = {2019}, - keywords = {Experiment}, - pages = {100699}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5LCIY3YG\\Yajima et al. - 2019 - Kinetics of deuterium penetration into neutron-irr.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7DJ7A9CR\\S2352179118300516.html:text/html}, + urldate = {2021-03-30}, + journal = {Journal of Nuclear Materials}, + author = {Valles, G. and Martin-Bragado, I. and Nordlund, K. and Lasa, A. and Björkas, C. and Safi, E. and Perlado, J. M. and Rivera, A.}, + month = jul, + year = {2017}, + keywords = {Tungsten, Fuzz nanostructures, Helium irradiation, OKMC simulations, Temperature}, + pages = {108--114}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PXEATDJS\\Valles et al. - 2017 - Temperature dependence of underdense nanostructure.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\3GN6KZMT\\S0022311516312478.html:text/html}, } -@article{nagata_helium_2002, - title = {Helium and hydrogen trapping in {W} and {Mo} single-crystals irradiated by {He} ions}, - volume = {307-311}, +@article{raiman_aggregation_2018, + series = {Special {Section} on "18th {International} {Conference} on {Fusion} {Reactor} {Materials}"}, + title = {Aggregation and data analysis of corrosion studies in molten chloride and fluoride salts}, + volume = {511}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311502012692}, - doi = {10.1016/S0022-3115(02)01269-2}, - abstract = {Retention of He and accumulation of H in the near surface layer of W and Mo single-crystals were studied during and after the implantation of He ions with 2–10 keV at 295 and 820 K. The He retention was saturated at a concentration of a He/metal ratio of about 0.25, depending on the implantation temperature. Subsequent He implantation caused H accumulation in the He saturated layer, up to a maximum concentration about equal to that of He. The initial H uptake rate just after the He irradiation was comparable to the impingement rate of the H2 or H2O molecule at the crystal surface from the residual gas. For the He irradiation at 820 K, blisters and exfoliation with large sizes were observed on the crystal surface, where impurities other than H and He were also enriched.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311518303957}, + doi = {10.1016/j.jnucmat.2018.07.036}, + abstract = {Corrosion studies in molten fluoride and chloride salts were surveyed, and key data were aggregated into a single dataset. Studies were graphed by salt purity, temperature, sample material, container material, and experimental method (loop, capsule, crucible). To elucidate and quantify the factors that affect corrosion in molten salts, a data analysis using a newly-defined corrosion resistance score and a correlation analysis using techniques borrowed from machine learning were performed. It is shown that salt purity had the strongest correlation with corrosion rates in molten chlorides and fluorides. Data analysis across varied works was inconsistent due to the lack of standardization among molten salt corrosion studies.}, language = {en}, - urldate = {2019-11-04}, + urldate = {2021-03-27}, journal = {Journal of Nuclear Materials}, - author = {Nagata, S. and Tsuchiya, B. and Sugawara, T. and Ohtsu, N. and Shikama, T.}, + author = {Raiman, Stephen S. and Lee, Sangkeun}, month = dec, - year = {2002}, - keywords = {Experiment}, - pages = {1513--1516}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4WYNUQQ4\\Nagata et al. - 2002 - Helium and hydrogen trapping in W and Mo single-cr.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KPFK5N8I\\S0022311502012692.html:text/html}, + year = {2018}, + keywords = {Corrosion, Molten salt, Molten salt reactor, MSR, Chloride, Concentrated solar, CSP, Fluoride}, + pages = {523--535}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5JFZKMLB\\S0022311518303957.html:text/html}, } -@article{paul_dynamics_1995, - series = {Honour {Biography} {David} {Smith}}, - title = {On the dynamics of the reaction of positive hydrogen cluster ions ({H5}+ to {H23}+) with para and normal hydrogen at 10 {K}}, - volume = {149-150}, - issn = {0168-1176}, - url = {http://www.sciencedirect.com/science/article/pii/016811769504269Q}, - doi = {10.1016/0168-1176(95)04269-Q}, - abstract = {The dynamics of clustering and fragmentation reactions Hi+ + 2H2 ⇌ Hi+2+ + H2, for odd i, was studied at a nominal temperature of 10 K in a 22-pole radio-frequency ion trap in normal hydrogen and para-enriched hydrogen. Ternary association rate coefficients, k3, and binary fragmentation rate coefficients, kf, were extracted from the measured temporal evolution of the hydrogen cluster ion intensity, I(Hi+), for i = 3,⋯,23. Pure para hydrogen enhances the rate coefficients for association and fragmentation. For i {\textgreater} 9 this general trend is explained by a difference in the capture cross-sections, kc, for the two hydrogen nuclear spin modifications. Significant differences in k3 which remain for small clusters (i {\textless} 9) are due to the availability of the J = 1 rotational energy of the ortho modification when merging into the cluster. This surprising result is discussed in the framework of simple dynamical and energetic considerations. Possible structures of the cluster can be classified and estimates for the bond energy of the outermost H2 in the cluster as a function of cluster size are derived.}, +@article{delaporte-mathurin_parametric_2021, + title = {Parametric optimisation based on {TDS} experiments for rapid and efficient identification of hydrogen transport materials properties}, + copyright = {All rights reserved}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179121000661}, + doi = {10.1016/j.nme.2021.100984}, + abstract = {A novel identification technique of hydrogen transport parameters using FESTIM (Finite Element Simulation of Tritium In Materials) has been demonstrated. FESTIM is a finite element code developed with FEniCS performing hydrogen transport simulations. The trapping parameters (detrapping energies and trap densities) are identified for various materials (Tungsten, Aluminium, EUROFER and Beryllium) by automatically reproducing thermo-desorption experiments. Several optimisation algorithms are tested and the Nelder–Mead algorithm shows the best efficiency. An optimisation test problem with five free parameters took only a few hours to solve whereas optimisation cases with two free parameters took a few minutes. Limitations of this technique are shown and discussed.}, language = {en}, - urldate = {2019-10-30}, - journal = {International Journal of Mass Spectrometry and Ion Processes}, - author = {Paul, W. and Lücke, B. and Schlemmer, S. and Gerlich, D.}, - month = nov, - year = {1995}, - keywords = {Experiment}, - pages = {373--387}, - file = {Paul et al. - 1995 - On the dynamics of the reaction of positive hydrog.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LRBRMHHZ\\Paul et al. - 1995 - On the dynamics of the reaction of positive hydrog.pdf:application/pdf}, + urldate = {2021-03-27}, + journal = {Nuclear Materials and Energy}, + author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, + month = mar, + year = {2021}, + keywords = {Materials, Finite elements, Automation, Hydrogen transport, Parametric optimisation}, + pages = {100984}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\96AN4EKH\\S2352179121000661.html:text/html}, } -@article{grisolia_tritium_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Tritium absorption and desorption in {ITER} relevant materials: comparative study of tungsten dust and massive samples}, - volume = {463}, - issn = {0022-3115}, - shorttitle = {Tritium absorption and desorption in {ITER} relevant materials}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514007739}, - doi = {10.1016/j.jnucmat.2014.10.089}, - abstract = {Tritium adsorption and desorption from well characterized tungsten dust are presented. The dust used are of different types prepared by planetary milling and by aggregation technique in plasma. For the milled powder, the surface specific area (SSA) is 15.5m2/g. The particles are poly-disperse with a maximum size of 200nm for the milled powder and 100nm for the aggregation one. Prior to tritiation the particles are carefully de-oxidized. Both samples are experiencing a high tritium inventory from 5GBq/g to 35GBq/g. From comparison with massive samples and considering that tritium inventory increases with SSA, it is shown that surface effects are predominant in the tritium trapping process. Extrapolation to the ITER environment is undertaken with the help of a Macroscopic Rate Equation model. It is shown that, during the life time of ITER, these particles can exceed rapidly 1GBq/g.}, - language = {en}, - urldate = {2019-10-25}, - journal = {Journal of Nuclear Materials}, - author = {Grisolia, C. and Hodille, E. and Chene, J. and Garcia-Argote, S. and Pieters, G. and El-Kharbachi, A. and Marchetti, L. and Martin, F. and Miserque, F. and Vrel, D. and Redolfi, M. and Malard, V. and Dinescu, G. and Acsente, T. and Gensdarmes, F. and Peillon, S. and Pegourié, B. and Rousseau, B.}, - month = aug, - year = {2015}, - keywords = {Experiment, Macroscopic rate equations}, - pages = {885--888}, - file = {Grisolia et al. - 2015 - Tritium absorption and desorption in ITER relevant.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TEFHUILY\\Grisolia et al. - 2015 - Tritium absorption and desorption in ITER relevant.pdf:application/pdf}, +@article{hurley_rohydrogene_nodate, + title = {Rôle de l'hydrogène dans la corrosion des alliages base {Nickel} en milieu primaire des {REP} : {Etude} cinétique des mécanismes d'absorption et de piégeage}, + language = {fr}, + author = {Hurley, Caitlin Mae}, + pages = {288}, + annote = {Thesis on A600 alloy (Ni-Cr-iron alloy). +Table 4.2 gives diffusion coefficients for H, D and T. + }, + file = {Hurley - Rôle de l'hydrogène dans la corrosion des alliages.pdf:D\:\\Logiciels\\data_zotero\\storage\\QAV764AC\\Hurley - Rôle de l'hydrogène dans la corrosion des alliages.pdf:application/pdf}, } -@incollection{ogorodnikova_trapping_2002, - address = {Dordrecht}, - series = {{NATO} {Science} {Series}}, - title = {Trapping {Effect} {In} {Hydrogen} {Retention} {In} {Metals}}, - isbn = {978-94-010-0444-2}, - abstract = {For the case of hydrogen interaction with a metal, modified equation for the timedependent change of trapped hydrogen has been derived. The present equation is essentially the same with previous models but slightly different in details, namely it is more general because covers all of previous models which are the particular cases of the present equation, it takes into account the difference in the structure of bcc and fcc metals, it does not include unknown parameters as in previous models such as attempt frequency (Wilson-Longhurst’s model) and trap radius (Myers-Doyle and Franzen’s models), but only well-known lattice parameter and diffusion coefficient from the literature. Comparison of the present model with Longhurst’s and Franzen’s models for hydrogen retention in tungsten shows that the present and Longhurst’s approaches differ by factor of six and Franzen’s approach results in about two orders of magnitude higher retention.}, +@article{zhou_water_2021, + title = {A {Water} cooled {Lead} {Ceramic} {Breeder} blanket for {European} {DEMO}}, + volume = {168}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621001733}, + doi = {10.1016/j.fusengdes.2021.112397}, + abstract = {The development of a demonstration fusion power plant (DEMO) is widely considered a crucial step beyond ITER leading toward fusion electricity. In a viable DEMO plant two major functions have to be achieved, namely to breed tritium for fuel self-sufficiency and to extract high-grade heat to allow an efficient electricity production. The breeding blanket is the key component to ensure these two functions. The solid breeder blanket is considered in the design of several ITER Test blankets and DEMO breeding blankets. In Europe, the helium cooled solid breeder blanket, so-called Helium Cooled Pebble Bed (HCPB) blanket, is one of the two driver blanket candidates selected for the European DEMO. In spite of the considerable progress and achievements, several potential issues inherent to the choice of the neutron multiplier and coolant remain with this concept. To overcome these challenges, research activities on an innovative concept (a Water cooled Lead Ceramic Breeder - WLCB), in which Lead/Lead-alloy is used as neutron multiplier, ceramic pebbles as tritium breeder, pressurized sub-cooled water as coolant, are on-going. This concept avoids the potential safety issue (exothermic hydrogen-producing Be-water reaction or PbLi-water reaction in case of water leakage) when Beryllium/Beryllide is used as neutron multiplier or lithium lead is used tritium breeder in a water cooled blanket concept. The neutronics, thermal hydraulics and mechanical performance figures of the above-mentioned innovative blanket concept are presented. This work concludes with possible future work and outlook towards the development of innovative alternative blanket concepts for the European demonstration fusion power plants.}, language = {en}, - urldate = {2019-10-07}, - booktitle = {Hydrogen and {Helium} {Recycling} at {Plasma} {Facing} {Materials}}, - publisher = {Springer Netherlands}, - author = {Ogorodnikova, O. V.}, - editor = {Hassanein, Ahmed}, - year = {2002}, - doi = {10.1007/978-94-010-0444-2_2}, - keywords = {Macroscopic rate equations}, - pages = {7--15}, + urldate = {2021-03-26}, + journal = {Fusion Engineering and Design}, + author = {Zhou, Guangming and Lu, Yudong and Hernández, Francisco A.}, + month = jul, + year = {2021}, + keywords = {DEMO, Neutronics, Breeding blanket, Thermal hydraulics, Thermomechanical assessment}, + pages = {112397}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\KVATZY4Y\\Zhou et al. - 2021 - A Water cooled Lead Ceramic Breeder blanket for Eu.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XIYPR9EW\\S0920379621001733.html:text/html}, } -@article{ohsawa_thermodynamics_2015, - title = {Thermodynamics of hydrogen-induced superabundant vacancy in tungsten}, - volume = {458}, +@article{noauthor_determination_1980, + title = {Determination of deuterium surface recombination rates on stainless steel}, + volume = {93-94}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514009714}, - doi = {10.1016/j.jnucmat.2014.12.029}, - abstract = {We investigate superabundant vacancy formation induced by hydrogen in tungsten in terms of an equilibrium thermodynamic model to estimate hydrogen isotope retention in plasma facing materials. Vacancy-hydrogen cluster concentrations in the bulk tungsten are calculated as a function of the H concentration at finite temperature. A monovacancy in usual bcc transition metals is capable of accommodating six H atoms, while a maximum of 12 H atoms can be accommodated in a tungsten monovacancy, according to first-principle calculations. The present results provide thermodynamic profiles of vacancy-hydrogen clusters trapping more than six H atoms for the first time. In present work, configurational transitions of H atoms trapped in the monovacancy and activation energies for them are investigated by examining the transition paths in order to calculate configurational entropy. Vacancy-hydrogen clusters trapping more than six H atoms exist in thermodynamic equilibrium. However, the major vacancy-hydrogen clusters are composed of six H atoms in a wide range of temperature and H concentration.}, - urldate = {2019-10-07}, + url = {http://www.sciencedirect.com/science/article/pii/0022311580902196}, + doi = {10.1016/0022-3115(80)90219-6}, + abstract = {The recombination rate coefficient kr (molecules · cm2/atoms2 · s), is experimentally determined by measuring the release rate of deuterium to the gas…}, + language = {en}, + urldate = {2021-03-24}, journal = {Journal of Nuclear Materials}, - author = {Ohsawa, Kazuhito and Nakamori, Fumihiro and Hatano, Yuji and Yamaguchi, Masatake}, - month = mar, - year = {2015}, - keywords = {Density Functional Theory}, - pages = {187--197}, - file = {Ohsawa et al. - 2015 - Thermodynamics of hydrogen-induced superabundant v.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\J88THL3Y\\Ohsawa et al. - 2015 - Thermodynamics of hydrogen-induced superabundant v.pdf:application/pdf}, + month = oct, + year = {1980}, + note = {Publisher: North-Holland}, + pages = {861--865}, + annote = {coefficient de recombinaison H dans l'acier}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7UPDLW8V\\0022311580902196.html:text/html}, } -@article{hodille_simulations_2017, - title = {Simulations of atomic deuterium exposure in self-damaged tungsten}, - volume = {57}, - issn = {0029-5515}, - doi = {10.1088/1741-4326/aa5aa5}, - abstract = {Simulations of deuterium (D) atom exposure in self-damaged polycrystalline tungsten at 500 K and 600 K are performed using an evolution of the MHIMS (migration of hydrogen isotopes in materials) code in which a model to describe the interaction of D with the surface is implemented. The surface-energy barriers for both temperatures are determined analytically with a steady-state analysis. The desorption energy per D atom from the surface is 0.69 ± 0.02 eV at 500 K and 0.87 ± 0.03 eV at 600 K. These values are in good agreement with ab initio calculations as well as experimental determination of desorption energies. The absorption energy (from the surface to the bulk) is 1.33 ± 0.04 eV at 500 K, 1.55 ± 0.02 eV at 600 K when assuming that the resurfacing energy (from the bulk to the surface) is 0.2 eV. Thermal-desorption spectrometry data after D atom exposure at 500 K and isothermal desorption at 600 K after D atom exposure at 600 K can be reproduced quantitatively with three bulk-detrapping energies, namely 1.65 ± 0.01 eV, 1.85 ± 0.03 eV and 2.06 ± 0.04 eV, in addition to the intrinsic detrapping energies known for undamaged tungsten (0.85 eV and 1.00 eV). Thanks to analyses of the amount of traps during annealing at different temperatures and ab initio calculations, the 1.65 eV detrapping energy is attributed to jogged dislocations and the 1.85 eV detrapping energy is attributed to dislocation loops. Finally, the 2.06 eV detrapping energy is attributed to D trapping in cavities based on literature reporting observations on the growth of cavities, even though this could also be understood as D desorbing from the C-D bond in the case of hydrocarbon contamination in the experimental sample.}, +@article{pecovnik_experiments_2021, + title = {Experiments and modelling of multiple sequential {MeV} ion irradiations and deuterium exposures in tungsten}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311521001707}, + doi = {10.1016/j.jnucmat.2021.152947}, + abstract = {Bulk tungsten samples were irradiated sequentially with 20 MeV tungsten ions and exposed to deuterium plasma. The experiments were performed in order to simulate the displacement damage that fusion neutrons will cause in a tungsten plasma-facing component of a future fusion device. To study the influence of the presence of hydrogen isotopes during the creation of displacement damage on the final defect density, tungsten irradiation and deuterium decoration cycles were performed up to three times. Deuterium depth profiling with 3He Nuclear Reaction Analysis and Thermal Desorption Spectroscopy showed that the deuterium concentration increased after each additional tungsten irradiation and deuterium exposure. After the third cycle, the deuterium concentration reached a maximum of 3.6 at.\% at the given plasma exposure temperature of 370 K. We attribute this increase in retention to the stabilization of the displacement damage during the tungsten irradiation by the presence of deuterium. The experimental results were simulated using the MHIMS-R macroscopic rate-equation code, which was recently upgraded with a damage stabilization term to describe experiments where tungsten was irradiated with MeV tungsten ions and simultaneously exposed to low-energy deuterium ions. Using this novel model, it was possible to quantitatively describe also the present results for the sequential irradiation/exposure scheme, with model parameters that were congruent with parameters derived from the simultaneous experiment. Modelling shows that kinetic de-trapping of trapped deuterium takes place during irradiation However, it is not the dominant process that explains defect stabilization. In addition, the model facilitates the extrapolation of present experimental results to an even larger number of sequential tungsten irradiation and deuterium exposure cycles. The model predicts that after about five sequential irradiation and plasma exposure cycles, a stationary state is reached with an associated maximum trapped D concentration of 4.2 at.\% for the given exposure temperature of 370 K.}, language = {en}, - number = {5}, - urldate = {2019-10-07}, - journal = {Nuclear Fusion}, - author = {Hodille, E. A. and Založnik, A. and Markelj, S. and Schwarz-Selinger, T. and Becquart, C. S. and Bisson, R. and Grisolia, C.}, + urldate = {2021-03-24}, + journal = {Journal of Nuclear Materials}, + author = {Pečovnik, M. and Schwarz-Selinger, T. and Markelj, S.}, month = mar, - year = {2017}, - keywords = {Macroscopic rate equations}, - pages = {056002}, - file = {Hodille et al. - 2017 - Simulations of atomic deuterium exposure in self-d.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8CA3YWFD\\Hodille et al. - 2017 - Simulations of atomic deuterium exposure in self-d.pdf:application/pdf}, + year = {2021}, + keywords = {Tungsten, Deuterium retention, Damage model, Damage stabilisation, Displacement damage}, + pages = {152947}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\JDF4PX5C\\S0022311521001707.html:text/html}, } -@article{marian_recent_2017, - title = {Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions}, - volume = {57}, - issn = {0029-5515}, - doi = {10.1088/1741-4326/aa5e8d}, - abstract = {Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, structural and plasma-facing materials will be exposed to unprecedented conditions of irradiation, heat flux, and temperature. While such extreme environments remain inaccessible experimentally, computational modeling and simulation can provide qualitative and quantitative insights into materials response and complement the available experimental measurements with carefully validated predictions. For plasma-facing components such as the first wall and the divertor, tungsten (W) has been selected as the leading candidate material due to its superior high-temperature and irradiation properties, as well as for its low retention of implanted tritium. In this paper we provide a review of recent efforts in computational modeling of W both as a plasma-facing material exposed to He deposition as well as a bulk material subjected to fast neutron irradiation. We use a multiscale modeling approach—commonly used as the materials modeling paradigm—to define the outline of the paper and highlight recent advances using several classes of techniques and their interconnection. We highlight several of the most salient findings obtained via computational modeling and point out a number of remaining challenges and future research directions.}, +@article{candido_novel_2021, + title = {A novel approach to the study of magnetohydrodynamic effect on tritium transport in {WCLL} breeding blanket of {DEMO}}, + volume = {167}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379621001101}, + doi = {10.1016/j.fusengdes.2021.112334}, + abstract = {The Water-Cooled Lithium Lead (WCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. Tritium can permeate into the different structural materials, arising potential issues concerning the fuel self-sufficiency and can be lost into the environment with consequent radiological hazard for the population. Within this frame, a tritium transport analysis is fundamental to evaluate tritium retention in LiPb (15.7 at. \% Li) and in the structures and tritium permeation fluxes into the cooling water. To assess this study, a portion of the breeder unit of the outboard equatorial module of the WCLL was modelled. The buoyancy forces and the magnetohydrodynamic (MHD) effect were also included. The final system of partial differential equations was solved with a novel approach through COMSOL Multiphysics. The coupled MHD and heat transfer system of equations was solved performing a transient simulation, that was stopped when the main average variables, temperature and velocity, reached a stable condition. In this way, it was possible to determine the lithium-lead velocity field and to use it as an input for the transport analysis. Tritium transport was modelled by using the input data of tritium generation rate and volumetric power deposition coming from an ad-hoc Monte Carlo simulation realized with MCNP software. Moreover, the transport analysis included advection-diffusion of tritium into the LiPb, transfer of tritium from the liquid interface towards the steel, diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant, advection-diffusion of diatomic tritium into the coolant.}, language = {en}, - number = {9}, - urldate = {2019-10-25}, - journal = {Nuclear Fusion}, - author = {Marian, Jaime and Becquart, Charlotte S. and Domain, Christophe and Dudarev, Sergei L. and Gilbert, Mark R. and Kurtz, Richard J. and Mason, Daniel R. and Nordlund, Kai and Sand, Andrea E. and Snead, Lance L. and Suzudo, Tomoaki and Wirth, Brian D.}, + urldate = {2021-03-22}, + journal = {Fusion Engineering and Design}, + author = {Candido, Luigi and Alberghi, Ciro and Moro, Fabio and Noce, Simone and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, month = jun, - year = {2017}, - keywords = {Density Functional Theory, Macroscopic rate equations, Monte Carlo, Cluster dynamics}, - pages = {092008}, - file = {Marian et al. - 2017 - Recent advances in modeling and simulation of the .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6S8WXTGQ\\Marian et al. - 2017 - Recent advances in modeling and simulation of the .pdf:application/pdf}, + year = {2021}, + keywords = {DEMO, WCLL, Tritium transport, MHD, MCNP}, + pages = {112334}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\CJL333UC\\Candido et al. - 2021 - A novel approach to the study of magnetohydrodynam.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZBH8SFNT\\S0920379621001101.html:text/html}, } -@article{matveev_reaction-diffusion_2018, - title = {Reaction-diffusion modeling of hydrogen transport and surface effects in application to single-crystalline {Be}}, - volume = {430}, - issn = {0168-583X}, - url = {http://www.sciencedirect.com/science/article/pii/S0168583X18303537}, - doi = {10.1016/j.nimb.2018.05.037}, - abstract = {A model based on a reaction-diffusion approach is used to simulate thermal desorption experiments performed with ion beam exposed single-crystalline beryllium. The model describes deuterium retention, migration and release, relating microscopic material properties to desorption spectra observed in experiments. Multiple trapping at single vacancies, hydrogen accumulation on the surface and surface coverage dependent desorption are accounted for in the model, showing good qualitative agreement with experimental observations.}, +@article{lee_kinetics_2019, + title = {A {Kinetics} of {Hydrogen} {Reduction} of {Nickel} {Oxide} at {Moderate} {Temperature}}, + volume = {25}, + issn = {2005-4149}, + url = {https://doi.org/10.1007/s12540-019-00261-y}, + doi = {10.1007/s12540-019-00261-y}, + abstract = {Nano-metallic nickel powders are highly-valued materials applied in energy, electronic devices and aerospace, which is known to be produced by the gaseous phase reduction method of NiCl2. In the case of a gaseous reduction method, size control is difficult due to the agglomeration of nickel powders. Therefore, a method of producing highly-valued nickel nano-powders from Ni(OH)2 has been proposed. Considering the reduction behavior of bulk nickel oxide has been reported to follow the topo-chemical model. However, reduction behavior of nano-particle is expected to be unknown state. It is necessary to clarify the mechanism of nickel oxide nano-particle reduction. Therefore, in this study, the temperature dependence and particle size dependence on the reduction behavior of from micro scale to nano scale particle was confirmed through TGA experiment. Also, the reduction mechanism of nickel oxide powder was also investigated based on kinetic considerations using the grain topo-chemical model. It was confirmed that the reduction reaction of nickel oxide powder undergoes through the 2nd Avrami model and reduction rate can be expressed by function of temperature and particle size of the powder. Due to the part of the diffusion, the particle size of the powder also affects the rate constant of the reduction reaction.\$\$\{{\textbackslash}text\{g\}\}\_\{\{(\{{\textbackslash}text\{x\}\})\}\} = \{{\textbackslash}text\{k\}\} {\textbackslash}cdot \{{\textbackslash}text\{f\}\}(\{{\textbackslash}text\{d\}\}) {\textbackslash}cdot \{{\textbackslash}text\{t\}\}\$\$g(x)=k·f(d)·t}, language = {en}, - urldate = {2019-10-29}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Matveev, D. and Wensing, M. and Ferry, L. and Virot, F. and Barrachin, M. and Ferro, Y. and Linsmeier, Ch.}, - month = sep, - year = {2018}, - keywords = {Macroscopic rate equations}, - pages = {23--30}, - file = {Matveev et al. - 2018 - Reaction-diffusion modeling of hydrogen transport .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XNWMCIL5\\Matveev et al. - 2018 - Reaction-diffusion modeling of hydrogen transport .pdf:application/pdf}, + number = {4}, + urldate = {2021-03-19}, + journal = {Metals and Materials International}, + author = {Lee, Dong Soo and Min, Dong Joon}, + month = jul, + year = {2019}, + pages = {982--990}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HYTQCLHN\\Lee et Min - 2019 - A Kinetics of Hydrogen Reduction of Nickel Oxide a.pdf:application/pdf}, } -@article{bonnin_rate_2015, - series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, - title = {Rate equations modeling for hydrogen inventory studies during a real tokamak material thermal cycle}, - volume = {463}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311514007375}, - doi = {10.1016/j.jnucmat.2014.10.053}, - abstract = {Prediction and control of tritium inventory in plasma-facing components (PFCs) is a critical nuclear safety issue for ITER and future fusion devices. This goal can be achieved through rate equations models as presented here. We calibrate our models with thermal desorption spectrometry results to obtain a validated set of material parameters relevant to hydrogen inventory processes in bulk tungsten. The best fits are obtained with two intrinsic trap types, deep and shallow, and an extrinsic trap created by plasma irradiation and plastic deformation of the tungsten matrix associated with blister formation. We then consider a realistic cycle of plasma discharges consisting of 400s of plasma exposure followed by a resting period of 1000s, repeating for several hours. This cycle is then closed by a long “overnight” period, thus providing an estimate of the amount of tritium retained in the PFCs after a full day of standard operation.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Bonnin, X. and Hodille, E. and Ning, N. and Sang, C. and Grisolia, Ch.}, - month = aug, - year = {2015}, - keywords = {Macroscopic rate equations}, - pages = {970--973}, - file = {Bonnin et al. - 2015 - Rate equations modeling for hydrogen inventory stu.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PNSWKRZY\\Bonnin et al. - 2015 - Rate equations modeling for hydrogen inventory stu.pdf:application/pdf}, +@article{zhou_proton_2020, + title = {Proton irradiation-decelerated intergranular corrosion of {Ni}-{Cr} alloys in molten salt}, + volume = {11}, + copyright = {2020 The Author(s)}, + issn = {2041-1723}, + url = {https://www.nature.com/articles/s41467-020-17244-y}, + doi = {10.1038/s41467-020-17244-y}, + abstract = {The effects of ionizing radiation on materials often reduce to “bad news”. Radiation damage usually leads to detrimental effects such as embrittlement, accelerated creep, phase instability, and radiation-altered corrosion. Here we report that proton irradiation decelerates intergranular corrosion of Ni-Cr alloys in molten fluoride salt at 650 °C. We demonstrate this by showing that the depth of intergranular voids resulting from Cr leaching into the salt is reduced by proton irradiation alone. Interstitial defects generated from irradiation enhance diffusion, more rapidly replenishing corrosion-injected vacancies with alloy constituents, thus playing the crucial role in decelerating corrosion. Our results show that irradiation can have a positive impact on materials performance, challenging our view that radiation damage usually results in negative effects.}, + language = {en}, + number = {1}, + urldate = {2021-03-19}, + journal = {Nature Communications}, + author = {Zhou, Weiyue and Yang, Yang and Zheng, Guiqiu and Woller, Kevin B. and Stahle, Peter W. and Minor, Andrew M. and Short, Michael P.}, + month = jul, + year = {2020}, + note = {Number: 1 +Publisher: Nature Publishing Group}, + pages = {3430}, + file = {Zhou et al. - 2020 - Proton irradiation-decelerated intergranular corro.pdf:D\:\\Logiciels\\data_zotero\\storage\\QXLZI3HJ\\Zhou et al. - 2020 - Proton irradiation-decelerated intergranular corro.pdf:application/pdf}, } -@article{benannoune_numerical_2019, - title = {Numerical simulation by finite element modelling of diffusion and transient hydrogen trapping processes in plasma facing components}, - volume = {19}, +@article{pitts_physics_2019, + title = {Physics basis for the first {ITER} tungsten divertor}, + volume = {20}, issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179118301169}, - doi = {10.1016/j.nme.2019.01.023}, - abstract = {In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures full 3D Macroscopic Rate Equation (MRE) modelling is proposed based on a finite element method (FEM). The model, implemented in the 3DS Abaqus software, uses a generalized transport equation, which accounts for mechanical fields, hydrogen transport and trapping, and their evolution with time. The influence of a-priori known thermal field has also been included. To ensure the solution convergence and the numerical stability, the trapping kinetic is introduced by using an approximation of the analytical solution the McNabb and Foster equation. Comparisons with a relevant 1D MRE code and with thermal programmed desorption (TPD) experimental results are performed on a 1D configuration to validate the model. Next, the model is used to simulate the tritium diffusion and trapping in a 2D geometry of interest in the upper plug of ITER tokamak, and results of tritium inventory are compared with an equivalent 1D calculation.}, - urldate = {2019-10-07}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179119300237}, + doi = {10.1016/j.nme.2019.100696}, + abstract = {On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ∼50\% higher than the previously accepted value of ∼10 MW m−2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events.}, + language = {en}, + urldate = {2020-06-24}, journal = {Nuclear Materials and Energy}, - author = {Benannoune, S. and Charles, Y. and Mougenot, J. and Gaspérini, M. and De Temmerman, G.}, - month = may, + author = {Pitts, R. A. and Bonnin, X. and Escourbiac, F. and Frerichs, H. and Gunn, J. P. and Hirai, T. and Kukushkin, A. S. and Kaveeva, E. and Miller, M. A. and Moulton, D. and Rozhansky, V. and Senichenkov, I. and Sytova, E. and Schmitz, O. and Stangeby, P. C. and De Temmerman, G. and Veselova, I. and Wiesen, S.}, + month = aug, year = {2019}, - keywords = {Macroscopic rate equations}, - pages = {42--46}, - file = {Benannoune et al. - 2019 - Numerical simulation by finite element modelling o.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\T99M696W\\Benannoune et al. - 2019 - Numerical simulation by finite element modelling o.pdf:application/pdf}, + keywords = {Tungsten, ITER, Divertor, Heat fluxes, SOLPS}, + pages = {100696}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FCM9SWUK\\Pitts et al. - 2019 - Physics basis for the first ITER tungsten divertor.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9BNNLRW3\\S2352179119300237.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\C5UCVAZA\\Pitts et al. - 2019 - Physics basis for the first ITER tungsten divertor.pdf:application/pdf}, } -@article{sang_modelling_2014, - series = {Proceedings of the 11th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-11 ({ISFNT}-11) {Barcelona}, {Spain}, 15-20 {September}, 2013}, - title = {Modelling of hydrogen isotope retention in the tungsten divertor of {EAST} during {ELMy} {H}-mode}, - volume = {89}, +@article{meszaros_definition_2015, + series = {Proceedings of the 28th {Symposium} {On} {Fusion} {Technology} ({SOFT}-28)}, + title = {Definition of the basic {DEMO} tokamak geometry based on systems code studies}, + volume = {98-99}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379614000416}, - doi = {10.1016/j.fusengdes.2014.01.040}, - abstract = {In this work, we study hydrogen isotopes (HI) inventory inside tungsten plasma-facing materials during high confinement mode discharges with repetitive edge localized modes (ELMy H-mode) based on the operating parameters of the EAST device, since tungsten is considered as the primary plasma-facing material and the ELMy H-mode is an important operation regime for EAST and future devices. The upgraded Hydrogen Isotope Inventory Processes Code (HIIPC) is applied with the incident depth profile provided by SRIM-2013 to make the study. The code is first verified by comparison with experimental measurements. The effects of the incident ion energy and ion flux on the retention are then studied. Finally, using the parameters obtained from EAST diagnostics, the HI retention inside the W divertor during ELMy H-mode is studied, which indicates the retained HI can be increased dramatically mainly due to ion-induced trap sites by ELMs.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379615301265}, + doi = {10.1016/j.fusengdes.2015.06.097}, + abstract = {This paper describes the methodology that has been developed and applied to derive the principal geometry of the main DEMO tokamak systems, in particular the radial and vertical cross section based on the systems code output parameters, while exact parameters are described elsewhere [1]. This procedure reviews the analysis of the radial and vertical build provided by the system code to verify critical integration interfaces, e.g. missing or too large gaps and/or insufficient thickness of components, and updates these dimensions based on results of more detailed analyses (e.g. neutronics, plasma scenario modelling, etc.) that were carried out outside of the system code in the past years. As well as providing a 3D configuration model of the DEMO tokamak for integrated engineering analysis, the results can also be used to refine the systems code model. This method, subject to continuous refinement, controls the derivation of the main machine parameters and ensures their coherence vis-à-vis a number of agreed controlled physics and engineering assumptions.}, language = {en}, - number = {9}, - urldate = {2019-10-30}, + urldate = {2021-02-16}, journal = {Fusion Engineering and Design}, - author = {Sang, Chaofeng and Sun, Jizhong and Bonnin, Xavier and Wang, Liang and Du, Hailong and Huang, Yan and Wang, Dezhen}, + author = {Meszaros, Botond and Bachmann, Christian and Kemp, Richard and Federici, Gianfranco}, month = oct, - year = {2014}, - keywords = {Macroscopic rate equations}, - pages = {2214--2219}, - file = {Sang et al. - 2014 - Modelling of hydrogen isotope retention in the tun.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\STBIKPXD\\Sang et al. - 2014 - Modelling of hydrogen isotope retention in the tun.pdf:application/pdf}, + year = {2015}, + keywords = {Systems code, DEMO, Nuclear fusion, Configuration, Geometry, PROCESS}, + pages = {1556--1560}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DS32BLBM\\Meszaros et al. - 2015 - Definition of the basic DEMO tokamak geometry base.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Q2ZUDY8S\\Meszaros et al. - 2015 - Definition of the basic DEMO tokamak geometry base.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7A64DVGQ\\S0920379615301265.html:text/html}, } -@article{sang_modelling_2012, - title = {Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices}, - volume = {52}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/52/4/043003}, - doi = {10.1088/0029-5515/52/4/043003}, - abstract = {Hydrogen isotope inventory (HII) is a key issue for fusion devices such as ITER. Simultaneous use of Be, W and C as the wall material for different parts of plasma-facing components (PFCs) will bring in material mixing issues, which compound that of hydrogen isotope retention. To simulate the hydrogen inventory in the PFCs, we have developed a flexible standalone model called HIIPC (Hydrogen Isotope Inventory Processes Code). The particle-balance-based model for reaction–diffusion and HII in metal and porous media (mainly carbon and co-deposited layers) is presented, coupled with a heating model which can calculate the temperature distribution. Some sample results are given to illustrate the model's capabilities and show good qualitative agreement with the experiment.}, +@article{edemetti_impact_2020, + title = {On the impact of the heat transfer modelling approach on the prediction of {EU}-{DEMO} {WCLL} breeding blanket thermal performances}, + volume = {161}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379620305998}, + doi = {10.1016/j.fusengdes.2020.112051}, + abstract = {The Water-Cooled Lithium-Lead Breeding Blanket is a key component of a fusion power plant, in charge of ensure Tritium production, shield Vacuum Vessel and magnets and remove the heat power deposited by radiation and particles arising from plasma. The last function is fulfilled by First Wall and Breeding Zone independent cooling systems. Several layouts of BZ coolant system have been investigated in the last years to identify a configuration that might guarantee EUROFER temperature below the limit (550 °C) and good thermal-hydraulic performances (i.e. water outlet temperature of 328 °C). A research activity is conducted to study and compare different modelling approaches to simulate the heat transfer within the BZ liquid metal, assessing their impact on the numerical prediction of the WCLL blanket thermal performances. An approach will rely on the simulation of convective and diffusive heat transfer processes taking place within the liquid metal by means of a CFD tool based on the Finite Volume Method. Conversely, the other approach will roughly assume a pure diffusive heat transfer mechanism within the breeder, due to the very low velocities envisaged for its flow field. In this case the heat transfer performances will be preferably assessed by means of a commercial code based on the Finite Element Method. The analyses have been carried out with reference to the so called “WCLL BB 2018 V0.6″ equatorial cell. Advantages and issues from the thermal-hydraulic point of view are identified, the impact of the imposed boundary conditions and heat transfer properties, with the implemented correlations, on the respective results is critically discussed.}, language = {en}, - number = {4}, - journal = {Nuclear Fusion}, - author = {Sang, Chaofeng and Bonnin, Xavier and Warrier, Manoj and Rai, Abha and Schneider, Ralf and Sun, Jizhong and Wang, Dezhen}, - month = mar, - year = {2012}, - keywords = {Macroscopic rate equations}, - pages = {043003}, - file = {Sang et al. - 2012 - Modelling of hydrogen isotope inventory in mixed m.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4836Z5VL\\Sang et al. - 2012 - Modelling of hydrogen isotope inventory in mixed m.pdf:application/pdf}, + urldate = {2021-02-22}, + journal = {Fusion Engineering and Design}, + author = {Edemetti, Francesco and Martelli, Emanuela and Del Nevo, Alessandro and Giannetti, Fabio and Arena, Pietro and Forte, Ruggero and Di Maio, Pietro Alessandro and Caruso, Gianfranco}, + month = dec, + year = {2020}, + keywords = {WCLL, Breeding blanket, Blanket engineering, CFD, FEM}, + pages = {112051}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\36ADAL4Y\\S0920379620305998.html:text/html}, } -@article{matveev_modeling_2019, - title = {Modeling of {H}/{D} isotope-exchange in crystalline beryllium}, - volume = {20}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179118302655}, - doi = {10.1016/j.nme.2019.100682}, - abstract = {A reaction-diffusion model with surface occupation dependent desorption [D. Matveev et al., Nucl. Instr. Meth. B 430 (2018) 23–30] has been updated to handle multiple hydrogen species to simulate hydrogen/deuterium isotope-exchange experiments performed on polycrystalline beryllium samples under ultra-high vacuum laboratory conditions. In the experiments subsequent exposures of a sample to hydrogen and deuterium ion beams in direct and reverse implantation order were followed by thermal desorption spectroscopy measurements under a constant heating rate of 0.7 K/s. The recorded signals of masses 2 to 4 (H2, HD and D2) indicate that the second implanted isotope dominates clearly the low temperature release stage ( ≈ 450 K), while both isotopes show a comparable contribution to the high temperature desorption stage ( ≈ 700 K) with only minor effect of the implantation order attributed to a slightly deeper penetration of deuterium compared to hydrogen. Simulations of the implantation and subsequent thermal desorption of hydrogen isotopes are performed to assess the atomic processes behind the isotope-exchange. Simulations were performed under the assumption that the low temperature release stage is attributed to hydrogen/deuterium atoms retained on effective open surfaces (e.g. interconnected porosity) represented in the simulations by a surface with an effective surface area exceeding the nominal exposed surface area by a factor up to 100. Kinetic de-trapping from vacancies with multiple trapping levels and enhanced desorption at surface coverages close to saturation are addressed in the model as possible mechanisms promoting the isotope-exchange. Simulation results suggest the applicability of the model to describe isotope-exchange processes in crystalline beryllium and give a qualitative explanation of the observed experimental facts.}, - urldate = {2019-10-11}, - journal = {Nuclear Materials and Energy}, - author = {Matveev, D. and Hansen, P. and Dittmar, T. and Koslowski, H. R. and Linsmeier, Ch.}, - month = aug, - year = {2019}, - keywords = {Macroscopic rate equations}, - pages = {100682}, - file = {Matveev et al. - 2019 - Modeling of HD isotope-exchange in crystalline be.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DATVZ54C\\Matveev et al. - 2019 - Modeling of HD isotope-exchange in crystalline be.pdf:application/pdf}, +@article{delaporte-mathurin_parametric_2020, + title = {Parametric study of hydrogenic inventory in the {ITER} divertor based on machine learning}, + volume = {10}, + copyright = {2020 The Author(s)}, + issn = {2045-2322}, + url = {https://www.nature.com/articles/s41598-020-74844-w}, + doi = {10.1038/s41598-020-74844-w}, + abstract = {A parametric study is performed with the 2D FESTIM code for the ITER monoblock geometry. The influence of the monoblock surface temperature, the incident ion energy and particle flux on the monoblock hydrogen inventory is investigated. The simulated data is analysed with a Gaussian regression process and an inventory map as a function of ion energy and incident flux is given. Using this inventory map, the hydrogen inventory in the divertor is easily derived for any type of scenario. Here, the case of a detached ITER scenario with inputs from the SOLPS code is presented. For this scenario, the hydrogen inventory per monoblock is highly dependent of surface temperature and ranges from \$\$10{\textasciicircum}\{18\}\$\$1018to \$\$6 {\textbackslash}times 10{\textasciicircum}\{19\}\$\$6×1019H after a \$\$10{\textasciicircum}\{7\}\$\$107s exposure. The inventory evolves as a power law of time and is lower at strike points where the surface temperature is high. Hydrogen inventory in the whole divertor after a \$\$10{\textasciicircum}\{7\}\$\$107s exposure is estimated at approximately 8 g.}, + language = {en}, + number = {1}, + urldate = {2021-01-05}, + journal = {Scientific Reports}, + author = {Delaporte-Mathurin, Rémi and Hodille, Etienne and Mougenot, Jonathan and De Temmerman, Gregory and Charles, Yann and Grisolia, Christian}, + month = oct, + year = {2020}, + note = {Number: 1 +Publisher: Nature Publishing Group}, + pages = {17798}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MBUVUJ3Z\\Delaporte-Mathurin et al. - 2020 - Parametric study of hydrogenic inventory in the IT.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VUYGDUV6\\s41598-020-74844-w.html:text/html}, } -@article{hodille_macroscopic_2015, - title = {Macroscopic rate equation modeling of trapping/detrapping of hydrogen isotopes in tungsten materials}, - volume = {467}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311515300660}, - doi = {10.1016/j.jnucmat.2015.06.041}, - abstract = {Relevant parameters for trapping of Hydrogen Isotopes (HIs) in polycrystalline tungsten are determined with the MHIMS code (Migration of Hydrogen Isotopes in MaterialS) which is used to reproduce Thermal Desorption Spectrometry experiments. Three types of traps are found: two intrinsic traps (detrapping energy of 0.87 eV and 1.00 eV) and one extrinsic trap created by ion irradiation (detrapping energy of 1.50 eV). Then MHIMS is used to simulate HIs retention at different fluences and different implantation temperatures. Simulation results agree well with experimental data. It is shown that at 300 K the retention is limited by diffusion in the bulk. For implantation temperatures above 500 K, the retention is limited by trap creation processes. Above 600 K, the retention drops by two orders of magnitude as compared to the retention at 300 K. With the determined detrapping energies, HIs outgassing at room temperature is predicted. After ions implantation at 300 K, 45\% of the initial retention is lost to vacuum in 300 000 s while during this time the remaining trapped HIs diffuse twice as deep into the bulk.}, - urldate = {2019-10-07}, - journal = {Journal of Nuclear Materials}, - author = {Hodille, E. A. and Bonnin, X. and Bisson, R. and Angot, T. and Becquart, C. S. and Layet, J. M. and Grisolia, C.}, - month = dec, - year = {2015}, - keywords = {Macroscopic rate equations}, - pages = {424--431}, - file = {Hodille et al. - 2015 - Macroscopic rate equation modeling of trappingdet.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MB4IWHZA\\Hodille et al. - 2015 - Macroscopic rate equation modeling of trappingdet.pdf:application/pdf}, +@phdthesis{dethloff_modeling_nodate, + title = {Modeling of {Helium} {Bubble} {Nucleation} and {Growth} in {Neutron} {Irradiated} {RAFM} {Steels}}, + language = {en}, + author = {Dethloff, Christian}, + file = {Dethloff - Modeling of Helium Bubble Nucleation and Growth in.pdf:D\:\\Logiciels\\data_zotero\\storage\\FU3BSUJ6\\Dethloff - Modeling of Helium Bubble Nucleation and Growth in.pdf:application/pdf}, } -@article{humrickhouse_implementation_2011, - title = {Implementation of {Tritium} {Permeation} {Models} in the {CFD} {Code} {Fluent}}, - volume = {60}, - issn = {1536-1055}, - doi = {10.13182/FST11-A12732}, - abstract = {A number of additions have been made to the computational fluid dynamics (CFD) code Fluent in order to model hydrogen permeation. In addition to fluid dynamics, Fluent solves for heat transfer in coupled solid and fluid regions, and solves advection-diffusion equations for scalar quantities such as hydrogen concentration. The latter have been modified with additional code to satisfy Sievert’s Law at solid-fluid interfaces and allow for temperature dependent diffusivity and permeability.The method has been employed to model the Tritium Heat Exchanger (THX) experiment at INL, which investigates hydrogen permeation in helium and candidate structural materials for high temperature gas reactor heat exchangers. The Arrhenius law parameters used in Fluent for Inconel 617 are initially determined via a simplified analytical method, and the resulting model predictions compare favorably with experiment data.}, - number = {4}, - urldate = {2019-10-23}, - journal = {Fusion Science and Technology}, - author = {Humrickhouse, P. W. and Calderoni, P. and Merrill, B. J.}, +@article{moro_neutronic_2018, + series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, + title = {Neutronic analyses in support of the {WCLL} {DEMO} design development}, + volume = {136}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379618304071}, + doi = {10.1016/j.fusengdes.2018.04.113}, + abstract = {In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design. Neutronic analyses play a fundamental role in the development of the WCLL blanket, providing guidelines for its design based on the evaluation of the nuclear performances. A detailed three-dimensional MCNP model of the latest WCLL layout has been generated and integrated in a DEMO MCNP generic model suitably designed for neutronic analyses. Three-dimensional neutron and gamma transport simulations have been performed using the MCNP5v1.6 Monte Carlo code and JEFF 3.2 nuclear data libraries, in order to assess the WCLL-DEMO tritium self-sufficiency and the shielding capabilities of the breeding blanket/manifold system to protect the vacuum vessel and toroidal field coils. Furthermore, radial profiles of the neutron flux, nuclear heating, neutron damage and he-production have been assessed in the inboard and outboard equatorial planes. The outcome of the present study highlights the potential and suitability of the WCLL breeding blanket for the application to DEMO, both in terms of tritium production and shielding performances.}, + language = {en}, + urldate = {2021-02-22}, + journal = {Fusion Engineering and Design}, + author = {Moro, Fabio and Del Nevo, Alessandro and Flammini, Davide and Martelli, Emanuela and Mozzillo, Rocco and Noce, Simone and Villari, Rosaria}, month = nov, - year = {2011}, - keywords = {Macroscopic rate equations}, - pages = {1564--1567}, + year = {2018}, + keywords = {DEMO, WCLL, Neutronics, Nuclear, MCNP, Shielding, TBR}, + pages = {1260--1264}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MGVHC34W\\Moro et al. - 2018 - Neutronic analyses in support of the WCLL DEMO des.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5CF4QJWJ\\S0920379618304071.html:text/html}, } -@article{simmonds_expanding_2018, - title = {Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning: {Applied} to hydrogen uptake and release from tungsten}, - volume = {508}, - issn = {0022-3115}, - shorttitle = {Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311517315301}, - doi = {10.1016/j.jnucmat.2018.05.080}, - abstract = {Simulating the implantation and thermal desorption evolution in a reaction-diffusion model requires solving a set of coupled differential equations that describe the trapping and release of atomic species in Plasma Facing Materials (PFMs). These fundamental equations are well outlined by the Tritium Migration Analysis Program (TMAP) which can model systems with no more than three active traps per atomic species. To overcome this limitation, we have developed a Pseudo Trap and Temperature Partition (PTTP) scheme allowing us to lump multiple inactive traps into one pseudo trap, simplifying the system of equations to be solved. For all temperatures, we show the trapping of atoms from solute is exactly accounted for when using a pseudo trap. However, a single effective pseudo trap energy can not well replicate the release from multiple traps, each with its own detrapping energy. However, atoms held in a high energy trap will remain trapped at relatively low temperatures, and thus there is a temperature range in which release from high energy traps is effectively inactive. By partitioning the temperature range into segments, a pseudo trap can be defined for each segment to account for multiple high energy traps that are actively trapping but are effectively not releasing atoms. With increasing temperature, as in controlled thermal desorption, the lowest energy trap is nearly emptied and can be removed from the set of coupled equations, while the next higher energy trap becomes an actively releasing trap. Each segment is thus calculated sequentially, with the last time step of a given segment solution being used as an initial input for the next segment as only the pseudo and actively releasing traps are modeled. This PTTP scheme is then applied to experimental thermal desorption data for tungsten (W) samples damaged with heavy ions, which display six distinct release peaks during thermal desorption. Without modifying the TMAP7 source code the PTTP scheme is shown to successfully model the D retention in all six traps. We demonstrate the full reconstruction from the plasma implantation phase through the controlled thermal desorption phase with detrapping energies near 0.9, 1.1, 1.4, 1.7, 1.9 and 2.1 eV for a W sample damaged at room temperature.}, - language = {en}, - urldate = {2019-11-07}, - journal = {Journal of Nuclear Materials}, - author = {Simmonds, M. J. and Yu, J. H. and Wang, Y. Q. and Baldwin, M. J. and Doerner, R. P. and Tynan, G. R.}, - month = sep, - year = {2018}, - keywords = {Macroscopic rate equations}, - pages = {472--480}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EP497L3V\\Simmonds et al. - 2018 - Expanding the capability of reaction-diffusion cod.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2SMMZLR6\\S0022311517315301.html:text/html}, +@article{liao_first-principles_2020, + title = {First-principles study of helium behavior in nickel with noble gas incorporation}, + volume = {127}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.5145016}, + doi = {10.1063/1.5145016}, + number = {17}, + urldate = {2021-02-19}, + journal = {Journal of Applied Physics}, + author = {Liao, Liang-Xiang and Zhang, Xun and Ren, Cui-Lan and Zhang, Zheng-De and Huang, He-Fei and Ma, Guo-Hong and Huai, Ping}, + month = may, + year = {2020}, + note = {Publisher: American Institute of Physics}, + pages = {175903}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PHLZP55J\\1.html:text/html}, } -@article{hodille_estimation_2017, - title = {Estimation of the tritium retention in {ITER} tungsten divertor target using macroscopic rate equations simulations}, - volume = {T170}, - issn = {1402-4896}, - doi = {10.1088/1402-4896/aa8787}, - abstract = {Based on macroscopic rate equation simulations of tritium migration in an actively cooled tungsten (W) plasma facing component (PFC) using the code MHIMS (migration of hydrogen isotopes in metals), an estimation has been made of the tritium retention in ITER W divertor target during a non-uniform exponential distribution of particle fluxes. Two grades of materials are considered to be exposed to tritium ions: an undamaged W and a damaged W exposed to fast fusion neutrons. Due to strong temperature gradient in the PFC, Soret effect’s impacts on tritium retention is also evaluated for both cases. Thanks to the simulation, the evolutions of the tritium retention and the tritium migration depth are obtained as a function of the implanted flux and the number of cycles. From these evolutions, extrapolation laws are built to estimate the number of cycles needed for tritium to permeate from the implantation zone to the cooled surface and to quantify the corresponding retention of tritium throughout the W PFC.}, +@article{federici_european_2017, + title = {European {DEMO} design strategy and consequences for materials}, + volume = {57}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/57/9/092002}, + doi = {10.1088/1741-4326/57/9/092002}, + abstract = {Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather ‘proxies’ of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed ‘low extrapolation’ system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device.}, language = {en}, - urldate = {2019-10-07}, - journal = {Physica Scripta}, - author = {Hodille, E. A. and Bernard, E. and Markelj, S. and Mougenot, J. and Becquart, C. S. and Bisson, R. and Grisolia, C.}, - month = oct, + number = {9}, + urldate = {2021-02-16}, + journal = {Nuclear Fusion}, + author = {Federici, G. and Biel, W. and Gilbert, M. R. and Kemp, R. and Taylor, N. and Wenninger, R.}, + month = jun, year = {2017}, - keywords = {Macroscopic rate equations}, - pages = {014033}, - file = {Hodille et al. - 2017 - Estimation of the tritium retention in ITER tungst.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KE2SBJ4Q\\Hodille et al. - 2017 - Estimation of the tritium retention in ITER tungst.pdf:application/pdf}, + note = {Publisher: IOP Publishing}, + pages = {092002}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5S9Q5QSA\\Federici et al. - 2017 - European DEMO design strategy and consequences for.pdf:application/pdf}, } -@article{de_temmerman_efficiency_2017, - series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, - title = {Efficiency of thermal outgassing for tritium retention measurement and removal in {ITER}}, - volume = {12}, - issn = {2352-1791}, - url = {http://www.sciencedirect.com/science/article/pii/S2352179116301284}, - doi = {10.1016/j.nme.2016.10.016}, - abstract = {As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg. Simulations and extrapolations from existing experiments indicate that T-retention in ITER will mainly be driven by co-deposition with beryllium (Be) eroded from the first wall, with co-deposits forming mainly in the divertor region but also possibly on the first wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is being designed to locally measure the T-retention in co-deposits forming on the inner divertor baffle of ITER. Regarding tritium removal, the baseline strategy is to perform baking of the plasma-facing components, at 513K for the FW and 623K for the divertor. Both baking and laser desorption rely on the thermal desorption of tritium from the surface, the efficiency of which remains unclear for thick (and possibly impure) co-deposits. This contribution reports on the results of TMAP7 studies of this efficiency for ITER-relevant deposits.}, - urldate = {2019-10-07}, - journal = {Nuclear Materials and Energy}, - author = {De Temmerman, G. and Baldwin, M. J. and Anthoine, D. and Heinola, K. and Jan, A. and Jepu, I. and Likonen, J. and Lungu, C. P. and Porosnicu, C. and Pitts, R. A.}, - month = aug, - year = {2017}, - keywords = {Macroscopic rate equations}, - pages = {267--272}, - file = {De Temmerman et al. - 2017 - Efficiency of thermal outgassing for tritium reten.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CTQQUCCZ\\De Temmerman et al. - 2017 - Efficiency of thermal outgassing for tritium reten.pdf:application/pdf}, +@article{hernandez_first_2018, + title = {First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors}, + volume = {137}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379618306392}, + doi = {10.1016/j.fusengdes.2018.09.014}, + abstract = {The current breeding blankets proposed in the different conceptual fusion power plants are based mainly on the use of Li4SiO4 and/or Li2TiO3 as tritium breeder and Be/Be12Ti as neutron multiplier or an eutectic Li17Pb83 for as a hybrid tritium and neutron multiplier. While these materials offer some tritium breeding capabilities, some recent studies show that the tritium self-sufficiency may not be ensured with these materials due to the strong reduction of blanket coverage after the integration of other in-vessel reactor systems (heating and current drive, limiters, large or double-null divertor systems, etc.). Also, some materials like Be raises several key feasibility concerns. The goal of this paper is to perform an update of the screening for tritium breeder and neutron multiplier materials and to assess the tritium breeding performance of the selected compounds in order to reveal new options. As for the neutron multiplier materials, a new subdivision between solid and liquid multipliers is proposed. For the selected compounds, detailed 3D heterogeneous neutronic analyses have been performed with MCNP5-1.60 assuming the architecture of the current EU DEMO Helium Cooled Pebble Bed (HCPB) as a benchmark breeding blanket. From the point of view of ceramic breeders, Li8ZrO6 has been found to outperform Li4SiO4 by more than 4\% in terms of tritium breeding, having 6\% higher melting point. From the point of view of solid neutron multipliers, Be12Cr, Be12V, Be13Zr and Be13Y show a similar performance as Be12Ti, while LaPb3, Zr5Pb4 and YPb2 offer a solution for a Be-free blanket. As for liquid multipliers, Pb in combination with a ceramic breeder shows a very promising option. Moreover, Pb compounds like Pb90Mn10 and Pb95Ba5 offer similar performance as Pb with a lower melting point (290 °C). Due to the significant advantages of molten Pb as neutron multiplier, future work will be conducted to define a design of a helium cooled Molten Lead Ceramic Breeder blanket, as simple, cost effective blanket concept.}, + language = {en}, + urldate = {2021-02-16}, + journal = {Fusion Engineering and Design}, + author = {Hernández, F. A. and Pereslavtsev, P.}, + month = dec, + year = {2018}, + keywords = {DEMO, Tritium breeding, Breeding blanket, TBR, Neutron multiplier}, + pages = {243--256}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\68Q37BXQ\\S0920379618306392.html:text/html}, } -@misc{noauthor_breeding_nodate, - title = {Breeding {Blankets} - an overview {\textbar} {ScienceDirect} {Topics}}, - url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/topics/engineering/breeding-blankets}, - urldate = {2020-12-14}, - file = {Breeding Blankets - an overview | ScienceDirect Topics:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IIENABQN\\breeding-blankets.html:text/html}, +@article{federici_plasma-material_2001, + title = {Plasma-material interactions in current tokamaks and their implications for next step fusion reactors}, + volume = {41}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/0029-5515/41/12/218}, + doi = {10.1088/0029-5515/41/12/218}, + abstract = {The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R\&D avenues for their resolution are presented.}, + language = {en}, + number = {12}, + urldate = {2021-02-11}, + journal = {Nuclear Fusion}, + author = {Federici, G. and Skinner, C. H. and Brooks, J. N. and Coad, J. P. and Grisolia, C. and Haasz, A. A. and Hassanein, A. and Philipps, V. and Pitcher, C. S. and Roth, J. and Wampler, W. R. and Whyte, D. G.}, + month = dec, + year = {2001}, + note = {Publisher: IOP Publishing}, + pages = {1967--2137}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\FNI9U9E5\\Federici et al. - 2001 - Plasma-material interactions in current tokamaks a.pdf:application/pdf}, } -@article{rubel_fusion_2019, - title = {Fusion {Neutrons}: {Tritium} {Breeding} and {Impact} on {Wall} {Materials} and {Components} of {Diagnostic} {Systems}}, - volume = {38}, - issn = {1572-9591}, - shorttitle = {Fusion {Neutrons}}, - url = {https://doi.org/10.1007/s10894-018-0182-1}, - doi = {10.1007/s10894-018-0182-1}, - abstract = {A concise overview is given on the impact of fusion neutrons on various classes of materials applied in reactor technology: plasma-facing, structural and functional tested for tritium production and for diagnostic systems. Tritium breeding in the reactor blanket, fuel cycle and separation of hydrogen isotopes are described together with issues related to primary (tritium) and induced radioactivity. Neutron-induced damage and degradation of material properties are addressed. Material testing under neutron fluxes and safety issues associated with handling components in the radioactive environment are described. A comprehensive list of references to monographs and research papers is included to help navigation in literature.}, +@incollection{zinkle_radiation-induced_2020, + title = {Radiation-{Induced} {Effects} on {Microstructure}}, + isbn = {978-0-08-102866-7}, + url = {https://linkinghub.elsevier.com/retrieve/pii/B9780128035818120752}, + language = {en}, + urldate = {2021-02-10}, + booktitle = {Comprehensive {Nuclear} {Materials}}, + publisher = {Elsevier}, + author = {Zinkle, Steven J.}, + year = {2020}, + doi = {10.1016/B978-0-12-803581-8.12075-2}, + pages = {91--129}, + file = {Zinkle - 2020 - Radiation-Induced Effects on Microstructure.pdf:D\:\\Logiciels\\data_zotero\\storage\\KNBSM85Z\\Zinkle - 2020 - Radiation-Induced Effects on Microstructure.pdf:application/pdf}, +} + +@article{dai_charpy_2005, + series = {Proceedings of the 6th {International} {Workshop} on {Spallation} {Materials} {Technology}}, + title = {Charpy impact tests on martensitic/ferritic steels after irradiation in {SINQ} target-3}, + volume = {343}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311505001650}, + doi = {10.1016/j.jnucmat.2004.12.020}, + abstract = {Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5dpa and 500appm He in a temperature range of 120–195°C. Results demonstrate that for all the four kinds of steels, the ductile-to-brittle transition temperature (DBTT) increases with irradiation dose. The difference in the DBTT shifts (ΔDBTT) of the different steels is not significant after irradiation in the SINQ target. The ΔDBTT data from the previous small punch (Δ DBTTSP) and the present Charpy impact (ΔDBTTCVN) tests can be correlated with the expression: Δ DBTTSP=0.4ΔDBTTCVN. All the ΔDBTT data fall into a linear band when they are plotted versus helium concentration. The results indicate that helium effects on the embrittlement of MF steels are significant, particularly at higher concentrations. It suggests that MF steels may not be very suitable for applications at low temperatures in spallation irradiation environments where helium production is high.}, language = {en}, - number = {3}, - urldate = {2020-12-14}, - journal = {Journal of Fusion Energy}, - author = {Rubel, Marek}, + number = {1}, + urldate = {2021-02-10}, + journal = {Journal of Nuclear Materials}, + author = {Dai, Yong and Marmy, Pierre}, month = aug, - year = {2019}, - pages = {315--329}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HDW2QJ4C\\Rubel - 2019 - Fusion Neutrons Tritium Breeding and Impact on Wa.pdf:application/pdf}, + year = {2005}, + pages = {247--252}, + annote = {This paper performs charpy impact tests on steel after irradiation and He production. +  +DBTT increases with He concentration}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\TXR3QMV5\\Dai et Marmy - 2005 - Charpy impact tests on martensiticferritic steels.pdf:application/pdf}, } -@article{federici_overview_2019, - title = {An overview of the {EU} breeding blanket design strategy as an integral part of the {DEMO} design effort}, - volume = {141}, +@article{farabolini_tritium_2006, + series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, + title = {Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor}, + volume = {81}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379619301590}, - doi = {10.1016/j.fusengdes.2019.01.141}, - abstract = {This paper provides an overview of the newly revised design and development strategy for the DEMO breeding blanket in Europe. This has been defined to take into account the input from the DEMO pre-conceptual design activities, the findings and recommendations of a thorough technical and programmatic assessment of the breeding blanket and the EU ITER Test Blanket Module (TBM) programs, conducted in 2017 by an independent expert panel. This work has led to the identification of (i) the most mature and technically sound breeding blanket concepts to be used as “driver” and “advanced” breeding blankets in DEMO, the latter to be installed and tested in a limited number of properly designed segments, potentially being more attractive for future fusion power plants; (ii) the remaining technical gaps and R\&D priorities. A number of urgent steps that are required to better align and strengthen the EU TBM and DEMO Breeding Blanket Program as a whole and to aim at an efficient implementation of the work are described in this paper. These include a proposal to change the EU TBM options to be tested in ITER in order to obtain important and useful information from the two current breeders (solid and liquid) and coolants (helium and water) considered for DEMO.}, + url = {http://www.sciencedirect.com/science/article/pii/S092037960500582X}, + doi = {10.1016/j.fusengdes.2005.07.018}, + abstract = {In this paper, we present computations linking the tritium release rate to the characteristics of lithium–lead and helium cooling circuits. Impacting component performances are evaluated such as tritium permeation towards the He coolant in the blanket modules, lithium–lead circulation rate, tritium extraction unit efficiency, tritium permeation in steam generator, helium coolant leak rate, helium purification unit maximum flow rate and efficiency. Safety considerations are also taken into account. A finite element model (FEM) for tritium permeation was developed considering various phenomena such as tritium transport by convection and diffusion in lithium–lead, MHD effects on liquid metal flows, tritium permeation in structures with temperature gradients. Other sub-system performances, like He leak rate and efficiency of tritium extraction systems, are discussed via an engineering approach. The results show that a reasonable compromise among the various requirements can be found, leading to technologically achievable requirements for tritium permeation barriers, tritium extraction systems both from Pb–17Li and He, and leak rates from the He cooling system.}, language = {en}, - urldate = {2020-12-14}, + number = {1}, + urldate = {2021-01-12}, journal = {Fusion Engineering and Design}, - author = {Federici, G. and Boccaccini, L. and Cismondi, F. and Gasparotto, M. and Poitevin, Y. and Ricapito, I.}, - month = apr, - year = {2019}, - keywords = {Tritium, DEMO, Breeding blanket, Design integration, Power plant}, - pages = {30--42}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\38H82YQF\\S0920379619301590.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RZNLSBXH\\Federici et al. - 2019 - An overview of the EU breeding blanket design stra.pdf:application/pdf}, + author = {Farabolini, W. and Ciampichetti, A. and Dabbene, F. and Fütterer, M. A. and Giancarli, L. and Laffont, G. and Puma, A. Li and Raboin, S. and Poitevin, Y. and Ricapito, I. and Sardain, P.}, + month = feb, + year = {2006}, + keywords = {Permeation, Tritium, Fusion blanket, Lithium–lead}, + pages = {753--762}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\RFVUBMUT\\Farabolini et al. - 2006 - Tritium control modelling for a helium cooled lith.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\7N36TTF5\\Farabolini et al. - 2006 - Tritium control modelling for a helium cooled lith.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TQ3ILGZX\\S092037960500582X.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\6HP5LMS7\\S092037960500582X.html:text/html}, } -@article{aubert_design_2020, - title = {Design and preliminary analyses of the new {Water} {Cooled} {Lithium} {Lead} {TBM} for {ITER}}, +@article{alberghi_magneto-convective_2020, + title = {Magneto-convective effect on tritium transport at breeder unit level for the {WCLL} breeding blanket of {DEMO}}, volume = {160}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620304695}, - doi = {10.1016/j.fusengdes.2020.111921}, - abstract = {In the European strategy, DEMO is the intermediate step between ITER and a commercial fusion power plant. In this framework, one of the goal of DEMO is to be a Breeding Blanket test facility. The Breeding Blanket, which is not present in ITER, is one of the key components for the future deployment of nuclear fusion electricity as it accomplishes the functions of tritium breeding and nuclear to thermal power conversion. Due to time constraints lead by the construction schedule of DEMO, a new strategy to consider in DEMO a “driver” Breeding Blanket that needs limited technological extrapolation has been chosen, while “advanced” Breeding Blanket concepts will be tested in the next phases. In this context, ITER will allow to test technologies to provide relevant contributions in terms of Return of eXperience to the DEMO “driver” Breeding Blanket project by the mean of Test Blanket Modules (TBM) to be installed in different ITER Vacuum Vessel Ports. Among the possible “driver” Breeding Blanket, the Water Cooled Lithium Lead (WCLL) concept comes out. In this framework, a realignment of the DEMO Breeding Blanket and TBM programs has started in 2017, leading to a new TBM development relevant of the DEMO WCLL BB. The WCLL TBM is therefore an essential component in ITER that will provide crucial information for the development of the DEMO “driver” blanket. This paper aims at presenting the development process and design status of WCLL TBM. After recalling the main features of the WCLL TBM, conceptual design analyses are presented and discussed.}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620305445}, + doi = {10.1016/j.fusengdes.2020.111996}, + abstract = {The Water-Cooled Lithium-Lead (WCLL) is one of the four breeding blanket concepts proposed by Europe in view of its DEMO reactor. The velocity field of the electrically conducting lead-lithium eutectic alloy inside the blanket is strongly influenced by the external magnetic field used for plasma confinement combined with buoyancy effect. The strength of the magnetohydrodynamics (MHD) effect and of the magneto-convective effect (MHD and buoyancy force) depends on the intensity of the magnetic field and its orientation with respect to the direction of the lead-lithium motion. This phenomenon significantly influences the resulting temperature and velocity fields, and therefore the tritium transport inside the breeding blanket. A multi-physics approach of a 3D tritium transport model is presented for a simplified geometry of the WCLL breeding blanket. In particular, advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel, diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant, and advection-diffusion of diatomic tritium into the coolant, temperature field, velocity fields of both lead-lithium and water, buoyancy forces, and MHD effect have been included in this study. The tritium concentrations and the inventories inside the lead-lithium, in the Eurofer pipes and in the baffle, and in the water coolant have been evaluated.}, language = {en}, - urldate = {2020-12-14}, + urldate = {2021-01-12}, journal = {Fusion Engineering and Design}, - author = {Aubert, J. and Aiello, G. and Alonso, D. and Batal, T. and Boullon, R. and Burles, S. and Cantone, B. and Cismondi, F. and Del Nevo, A. and Maqueda, L. and Morin, A. and Rodríguez, E. and Rueda, F. and Soldaini, M. and Vallory, J.}, + author = {Alberghi, Ciro and Candido, Luigi and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, month = nov, year = {2020}, - keywords = {ITER, Breeding Blanket, TBM, WCLL}, - pages = {111921}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ACGSCMZQ\\S0920379620304695.html:text/html;Aubert et al. - 2020 - Design and preliminary analyses of the new Water C.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4IR47KT8\\Aubert et al. - 2020 - Design and preliminary analyses of the new Water C.pdf:application/pdf}, + keywords = {DEMO, WCLL, Tritium transport, MHD, Breeding blanket, Buoyancy forces, Magneto-convection}, + pages = {111996}, + file = {Alberghi et al. - 2020 - Magneto-convective effect on tritium transport at .pdf:D\:\\Logiciels\\data_zotero\\storage\\6Z2ZTL2I\\Alberghi et al. - 2020 - Magneto-convective effect on tritium transport at .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MYAUY4V4\\S0920379620305445.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\RMI3A2WW\\S0920379620305445.html:text/html}, } -@article{aubert_status_2018, - series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, - title = {Status of the {EU} {DEMO} {HCLL} breeding blanket design development}, - volume = {136}, +@article{candido_tritium_2019, + series = {{SI}:{SOFT}-30}, + title = {Tritium transport model at breeder unit level for {WCLL} breeding blanket}, + volume = {146}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S092037961830423X}, - doi = {10.1016/j.fusengdes.2018.04.133}, - abstract = {In the framework of the European “HORIZON 2020” innovation and research programme, the EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO). One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. CEA-Saclay, with the support of Wigner-RCP and Centrum výzkumu Řež, is in charge of the development of one of the four BB concepts investigated in Europe for DEMO: the Helium Cooled Lithium Lead (HCLL) BB. The rationales of the HCLL are the use of Eurofer as structural material, eutectic liquid lithium-lead (PbLi) as tritium breeder and neutron multiplier, and helium gas as coolant. This paper shows the basic description of the DEMO HCLL BB concept and its design evolution during the past years, from a design based on the ITER Test Blanket Module (TBM) concept to a more advanced design called “Advanced-Plus” concept. This new HCLL BB concept that has been designed in order to improve Tritium Breeding Ratio (TBR) and shielding performances is presented. This new reference HCLL BB design has been analyzed and show very promising nuclear performances. Nevertheless, the “Optimized Conservative” concept, based on ITER TBM, is still considered as a robust back-up solution since structural improvements are still necessary on the “Advanced-Plus” concept. Moreover, a new Back Supporting Structure (BSS) is presented in this paper, designed to support the BB modules, with the aim to reduce pressure drops and thermal stresses.}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379619302170}, + doi = {10.1016/j.fusengdes.2019.02.041}, + abstract = {In a fusion power demonstration plant (DEMO), the development of a tritium transport model is mandatory in order to correctly predict the tritium concentration inside the liquid metal, the permeated flux through the structural materials and into the coolant, playing a fundamental role in guaranteeing tritium self-sufficiency in the fusion reactor and safety both for the workers and for the external environment. In the present work, a multi-physics 3D tritium transport model has been assessed for a single breeder unit located in the outboard equatorial module of the Water-Cooled Lithium Lead (WCLL) breeding blanket of DEMO, adopting an approach that permits to have a modelling tool able to be adaptive within certain margins to changes in operating parameters and geometry. The transport has been modelled considering advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel (adsorption/desorption), diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant (recombination/dissociation), advection-diffusion of diatomic tritium into the coolant. The effect of buoyancy forces, which arise due to temperature variation, has been also considered. Under the above-specified phenomena, tritium concentrations, inventories and losses have been derived.}, language = {en}, - urldate = {2020-12-14}, + urldate = {2021-01-12}, journal = {Fusion Engineering and Design}, - author = {Aubert, Julien and Aiello, Giacomo and Arena, Pietro and Barrett, Tom and Boccaccini, Lorenzo Virgilio and Bongiovì, Gaetano and Boullon, Rémi and Cismondi, Fabio and Critescu, Ion and Domalapally, Phani Kumar and Forest, Laurent and Jaboulay, Jean-Charles and Kiss, Béla and Morin, Alexandre and Peyraud, Justine and Porempovics, Gabor and Utili, Marco and Vála, Ladislav}, - month = nov, - year = {2018}, - keywords = {DEMO, Breeding Blanket, HCLL}, - pages = {1428--1432}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MYBZFDWH\\S092037961830423X.html:text/html;Aubert et al. - 2018 - Status of the EU DEMO HCLL breeding blanket design.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\F48N9ABH\\Aubert et al. - 2018 - Status of the EU DEMO HCLL breeding blanket design.pdf:application/pdf}, + author = {Candido, Luigi and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, + month = sep, + year = {2019}, + keywords = {DEMO, WCLL, Tritium transport, Breeding blanket, Buoyancy effect}, + pages = {1207--1210}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\N6WWPB59\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\KB3HXFIA\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\G5RUYKPC\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\RR3LV77Y\\S0920379619302170.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\8BDBXJIG\\S0920379619302170.html:text/html}, } -@article{boullon_development_2020, - title = {Development of a {WCLL} {DEMO} {First} {Wall} design module in the {SYCOMORE} system code interfaced with the neutronic one}, - volume = {153}, +@article{testoni_tritium_2019, + series = {{SI}:{SOFT}-30}, + title = {Tritium transport model at breeder unit level for {HCLL} breeding blanket}, + volume = {146}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620300624}, - doi = {10.1016/j.fusengdes.2020.111514}, - abstract = {The pre-conceptual design of the DEMOnstration reactors has already started and several tokamak configurations have to be tested to find the best design by exploring different design parameters. Fast simulations involving the different components behavior must be performed. Within the European framework, SYCOMORE (SYstem COde for MOdelling tokamak REactor) is developed by CEA for this purpose. The Breeding Blanket (BB) facing the plasma is a key component in DEMO ensuring tritium self-sufficiency, shielding against neutrons and heat extraction for electricity production. Several BB concepts are being studied, among which the Water Cooled Lithium Lead (WCLL) one. SYCOMORE includes several specific modules in Python linked together, one of which has been developed to define a suitable design of the WCLL Breeding Blanket and is presented in this paper. The method to define automatically the WCLL First Wall (FW) design using analytical design formulae starting from thermo-hydraulic and thermo-mechanical considerations as well as design criteria coming from Codes \& Standards (C\&S) is presented. Furthermore WCLL FW design obtained with SYCOMORE is compared to Finite Elements (FE) analyses of the DEMO WCLL BB. Finally, a coupling between thermo-mechanics and neutronics is implemented, several iterations are necessary to obtain a converged design. Neutronic block evaluates the radial build, the BB tritium production, and the nuclear heating in the FW and the Breeding Zone (used by thermo-mechanical block). Thermo-mechanical module gives the design data (FW thickness, compositions, etc.) to the neutronic block.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379619305137}, + doi = {10.1016/j.fusengdes.2019.03.180}, + abstract = {The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses. The present 2D transport model takes into account a single breeder unit located in the outboard equatorial module of the HCLL breeding blanket, which is one of the most loaded modules in normal operating conditions. A multi-physics approach has been adopted considering several physics phenomena, providing for buoyancy effect, temperature fields, tritium generation rate and velocity profile of lead-lithium and coolant. The transport has been modelled considering advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel (adsorption/desorption), diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant (recombination/desorption), advection-diffusion of diatomic tritium into the coolant. Tritium concentrations, inventories and losses have been derived under the above specified phenomena. In particular, the effect of buoyancy forces on the tritium transport has been implemented and compared with the condition without buoyancy.}, language = {en}, - urldate = {2020-12-14}, + urldate = {2021-02-10}, journal = {Fusion Engineering and Design}, - author = {Boullon, Rémi and Aubert, Julien and Jaboulay, Jean-Charles and Aiello, Giacomo}, - month = apr, - year = {2020}, - keywords = {DEMO, Breeding blanket, WCLL, SYCOMORE, System code}, - pages = {111514}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4T29JJMD\\S0920379620300624.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9W4U2CZL\\Boullon et al. - 2020 - Development of a WCLL DEMO First Wall design modul.pdf:application/pdf}, + author = {Testoni, Raffaella and Candido, Luigi and Utili, Marco and Zucchetti, Massimo}, + month = sep, + year = {2019}, + keywords = {DEMO, Tritium transport, Breeding blanket, HCLL, Buoyancy effect}, + pages = {2319--2322}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\24MIXHNW\\Testoni et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EK4EI8T5\\S0920379619305137.html:text/html}, } -@article{shah_brittle-ductile_2020, - title = {Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load}, - volume = {541}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/S0022311520310242}, - doi = {10.1016/j.jnucmat.2020.152416}, - abstract = {The lifetime of tungsten (W) monoblocks under fusion conditions is ambivalent. In this work, the microstructure dependent mechanical behaviour of pulsed high heat flux (HHF) exposed W monoblock is investigated. Two different microstructural states, i.e. initial (deformed) and recrystallized, both machined from HHF exposed monoblocks are tested using tensile and small punch tests. The initial microstructural state reveals a higher fraction of low angle boundaries along with a preferred orientation of crystals. Following HHF exposure, the recrystallized state exhibits weakening of initial texture along with a higher fraction of high angle boundaries. Irrespective of the testing methodology, both the microstructural states display brittle failure for temperatures lower than 400∘C. For higher temperatures ({\textgreater}400∘C), the recrystallized microstructure exhibits more ductile behaviour as compared to the initial state. The observed microstructural state-dependent mechanical behaviour is further discussed in terms of different microstructural features. The estimated brittle-to-ductile transition temperature (BDTT) range is noticed to be lower for the recrystallized state as compared to the initial state. The lower BDTT in the recrystallized state is attributed to the high purity of the W in combination with its low defect density, thereby preventing segregation of impurities at the recrystallized boundaries and the related premature failure. Based on this observation, it is concluded that the common opinion of the aggravation of BDTT in W due to recrystallization is not unerring, and as a matter of fact, recrystallization in W could be instrumental for preventing the self-castellation of the monoblocks.}, +@incollection{hashimoto_305_2020, + address = {Oxford}, + title = {3.05 - {Radiation} {Effects} in {Ferritic} {Steels} and {Advanced} {Ferritic}-{Martensitic} {Steels}☆}, + isbn = {978-0-08-102866-7}, + url = {https://www.sciencedirect.com/science/article/pii/B978012803581812051X}, + abstract = {The present review begins with a brief introduction to the development of ferritic and ferritic-martensitic steels summarizing the development history in each country. The main thrust is on the development of commercial ferritic steels for core components of fission, fast, and fusion reactors. Hence, the next part of the review introduces the irradiation effects in ferritic and ferritic-martensitic steels, including radiation damage mechanisms of core components in reactors. The irradiation response of ferritic steels with respect to microstructural evolution, swelling, irradiation hardening, irradiation embrittlement, and irradiation creep are highlighted. The main concerns of ferritic steels such as the inferior high temperature irradiation creep and severe embrittlement are addressed. Finally, the development of advanced creep-resistant ferritic steels like ODS steels, for fission and fusion applications are presented. The future trends in the application of ferritic steels in fast and fusion reactor technology are finally summarized.}, language = {en}, - urldate = {2020-12-07}, - journal = {Journal of Nuclear Materials}, - author = {Shah, V. and van Dommelen, J. A. W. and Altstadt, E. and Das, A. and Geers, M. G. D.}, - month = dec, + urldate = {2021-02-09}, + booktitle = {Comprehensive {Nuclear} {Materials} ({Second} {Edition})}, + publisher = {Elsevier}, + author = {Hashimoto, Naoyuki and Kasada, Ryuta and Raj, Baldev and Vijayalakshmi, M.}, + editor = {Konings, Rudy J. M. and Stoller, Roger E.}, + month = jan, year = {2020}, - keywords = {Tungsten, Brittle-to-ductile transition temperature (BDTT), High Heat Flux (HHF) exposure, Recrystallization and embrittlement, Tensile and small punch test}, - pages = {152416}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UIIRXFBF\\S0022311520310242.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SG5J3FWP\\S0022311520310242.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TG9AT4TN\\Shah et al. - 2020 - Brittle-ductile transition temperature of recrysta.pdf:application/pdf}, + doi = {10.1016/B978-0-12-803581-8.12051-X}, + keywords = {Irradiation, Evolution, Ferritic/martensitic steel, Hardening, Microstructural}, + pages = {226--254}, + annote = {This review work goes through the effects of He irradiation on mechanical properties of steel}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DAYZZL9J\\B978012803581812051X.html:text/html}, } -@article{delaporte-mathurin_parametric_2020, - title = {Parametric study of hydrogenic inventory in the {ITER} divertor based on machine learning}, - volume = {10}, - copyright = {2020 The Author(s)}, - issn = {2045-2322}, - url = {https://www.nature.com/articles/s41598-020-74844-w}, - doi = {10.1038/s41598-020-74844-w}, - abstract = {A parametric study is performed with the 2D FESTIM code for the ITER monoblock geometry. The influence of the monoblock surface temperature, the incident ion energy and particle flux on the monoblock hydrogen inventory is investigated. The simulated data is analysed with a Gaussian regression process and an inventory map as a function of ion energy and incident flux is given. Using this inventory map, the hydrogen inventory in the divertor is easily derived for any type of scenario. Here, the case of a detached ITER scenario with inputs from the SOLPS code is presented. For this scenario, the hydrogen inventory per monoblock is highly dependent of surface temperature and ranges from \$\$10{\textasciicircum}\{18\}\$\$1018to \$\$6 {\textbackslash}times 10{\textasciicircum}\{19\}\$\$6×1019H after a \$\$10{\textasciicircum}\{7\}\$\$107s exposure. The inventory evolves as a power law of time and is lower at strike points where the surface temperature is high. Hydrogen inventory in the whole divertor after a \$\$10{\textasciicircum}\{7\}\$\$107s exposure is estimated at approximately 8 g.}, +@article{chernov_peculiarities_2018, + title = {Peculiarities of helium porosity evolution in the ferritic–martensitic steels produced by spark plasma sintering}, + volume = {16}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179117300820}, + doi = {10.1016/j.nme.2018.07.010}, + abstract = {Oxide dispersion strengthened (ODS) ferritic–martensitic steels are considered as promising structural materials for fusion reactors, as well as for active zone of new generations fast reactors. In this connection, peculiarities of helium porosity formation and gaseous swelling have been investigated in the dispersion-strengthened EP-450 ODS steel with 0.3 and 1 wt.\% Y2O3 dispersant produced by spark plasma sintering (SPS) as compared with the matrix EP-450 steel, EP-450 ODS steel produced using a hot extrusion (HE) as well as reactor austenitic ChS-68 steel. The samples were irradiated by 40-keV Не+ ions at 923 K up to fluence of 5 × 1020 ion/m2. Microstructural investigations of irradiated samples were performed using a transmission electron microscope. It is found that plurality of zones with a very different type of helium porosity and different character of their distribution is developed in steel with 1 wt.\% Y2O3. Such zones are less in steel with 0.3 wt.\% Y2O3 as opposed to matrix EP-450 steel, EP-450 ODS steel obtained by HE, and austenitic ChS-68 reactor steel. It is found in comparing the character of helium porosity formation in the matrix steel EP-450, steel EP-450 ODS (HE) and EP-450 ODS (SPS) that bubbles are developed with a smaller average sizes and, therefore, helium swelling is lower in all ODS steels than that in steel EP-450, but for ODS steel made by SPS, swelling is significantly higher than in ODS steel produced by hot extrusion. At the same time, austenitic steel ChS-68 shows a minimum gaseous swelling for the used conditions of helium ion irradiation. An assumption is made that the extremely nonuniform distribution of helium bubbles (gas filled pores) both in volume and size in SPS steel is associated with the initially highly defect structure, including the residual porosity in 1–3\% as well as a result of strong redistribution of chromium between ferritic grains and grains of tempered martensite during manufacturing of samples.}, language = {en}, - number = {1}, - urldate = {2021-01-05}, - journal = {Scientific Reports}, - author = {Delaporte-Mathurin, Rémi and Hodille, Etienne and Mougenot, Jonathan and De Temmerman, Gregory and Charles, Yann and Grisolia, Christian}, - month = oct, - year = {2020}, - note = {Number: 1 + urldate = {2021-02-09}, + journal = {Nuclear Materials and Energy}, + author = {Chernov, I. I. and Staltsov, М. S. and Kalin, B. A. and Bogachev, I. A. and Korshunov, S. N.}, + month = aug, + year = {2018}, + keywords = {Ferritic–martensitic steel, Helium swelling, ODS steels, Oxide-dispersion strengthening, Spark-plasma sintering}, + pages = {249--257}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PT4G32KD\\Chernov et al. - 2018 - Peculiarities of helium porosity evolution in the .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\D6R2D2A7\\S2352179117300820.html:text/html}, +} + +@article{wei_evaluation_2016, + title = {Evaluation of irradiation hardening and microstructure evolution under the synergistic interaction of {He} and subsequent {Fe} ions irradiation in {CLAM} steel}, + volume = {676}, + issn = {0925-8388}, + url = {https://www.sciencedirect.com/science/article/pii/S0925838816307514}, + doi = {10.1016/j.jallcom.2016.03.167}, + abstract = {Sequential dual-ion irradiation is a useful technique for experimental exploration on the synergistic effects of ion accumulation and cascade damage. In this research, the helium-ion accumulation concomitant with displacement damage induced by helium and iron ions irradiation in China low active martensitic (CLAM) steel was studied by ion-irradiation, transmission electron microscopy and nano-indentation technique. The helium bubbles formed under continuous implantation of helium ions at room temperature and the helium dose forming observed bubbles resolved by TEM clearly in CLAM steel is around 0.7 × 1017–1.0 × 1017 He+/cm2 under single 100 keV He+ irradiation. Significant irradiation hardening was observed in the samples with various ion- and dose-irradiations. Positive correlation between the hardening increment and the helium-ion dose has been established in single helium-ion irradiated samples. On the other hand, the subsequent Fe-ion irradiation greatly promoted the formation and growth of helium bubbles as well as dislocation loops in sequential dual-ion irradiated samples. No significant contribution of the subsequent Fe-ion irradiation on the hardness increment was found for the sequential dual-ion irradiated samples. It is suggested that the defects recombination, the combination effects of size and density of defects contribute to the degree of irradiation hardening. The calculated hardness increment based on dispersion strengthening model and the experimental microstructure analysis followed the same trend as the experimental nano-indentation data.}, + language = {en}, + urldate = {2021-02-09}, + journal = {Journal of Alloys and Compounds}, + author = {Wei, Y. P. and Liu, P. P. and Zhu, Y. M. and Wang, Z. Q. and Wan, F. R. and Zhan, Q.}, + month = aug, + year = {2016}, + keywords = {Microstructure, CLAM steel, Ion-irradiation, Irradiation hardening, Nano-indentation, Transmission electron microscopy}, + pages = {481--488}, + annote = {This paper gives He concentration fields in steel computed by SRIM. +links to hardenning}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\222LPV6L\\Wei et al. - 2016 - Evaluation of irradiation hardening and microstruc.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\IIZNZAJP\\S0925838816307514.html:text/html}, +} + +@article{chen_dislocation_2008, + title = {Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress}, + volume = {56}, + issn = {1359-6454}, + url = {https://www.sciencedirect.com/science/article/pii/S1359645407006350}, + doi = {10.1016/j.actamat.2007.09.016}, + abstract = {The oxide dispersion strengthened (ODS) ferritic steel PM2000, was homogeneously implanted with α-particles under uniaxial tensile stresses ranging from 20 to 250MPa, causing irradiation creep. The irradiation temperatures were 573, 673, and 773K, respectively. Maximum helium concentrations of 3000appm were attained, causing a concurrent displacement dose of approximately 0.75dpa (damage rate about 5×10−6dpas−1). Microstructural changes were studied in detail by transmission electron microscopy (TEM). Two sets of dislocation loops were identified, both interstitial in nature, with Burgers vectors b={\textless}100{\textgreater} and b=½{\textless}111{\textgreater}, and habit planes of (100) and (111), respectively. No influence of stress applied during the irradiation creep tests on loop formation and growth could be detected. TEM investigation also showed the formation of bubbles attached to loops already during implantation at 573K, the formation of bubble–loop complexes at 673K, and Y2O3 particles changing their shape by the attachment of bubbles at 773K.}, + language = {en}, + number = {2}, + urldate = {2021-02-09}, + journal = {Acta Materialia}, + author = {Chen, J. and Jung, P. and Hoffelner, W. and Ullmaier, H.}, + month = jan, + year = {2008}, + keywords = {TEM, Creep, Dislocation, Implantation/irradiation, ODS ferritic steel}, + pages = {250--258}, + annote = {this paper shows bubbles in steel (up to 50nm of diameter)}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\TLTKA68N\\Chen et al. - 2008 - Dislocation loops and bubbles in oxide dispersion .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\A83N8HCX\\S1359645407006350.html:text/html}, +} + +@article{knaster_materials_2016, + title = {Materials research for fusion}, + volume = {12}, + copyright = {2016 Nature Publishing Group}, + issn = {1745-2481}, + url = {https://www.nature.com/articles/nphys3735}, + doi = {10.1038/nphys3735}, + abstract = {Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission reactors. The technological challenges of fusion energy are intimately linked with the availability of suitable materials capable of reliably withstanding the extremely severe operational conditions of fusion reactors. Although fission and fusion materials exhibit common features, fusion materials research is broader. The harder mono-energetic spectrum associated with the deuterium–tritium fusion neutrons (14.1 MeV compared to {\textless}2 MeV on average for fission neutrons) releases significant amounts of hydrogen and helium as transmutation products that might lead to a (at present undetermined) degradation of structural materials after a few years of operation. Overcoming the historical lack of a fusion-relevant neutron source for materials testing is an essential pending step in fusion roadmaps. Structural materials development, together with research on functional materials capable of sustaining unprecedented power densities during plasma operation in a fusion reactor, have been the subject of decades of worldwide research efforts underpinning the present maturity of the fusion materials research programme.}, + language = {en}, + number = {5}, + urldate = {2021-02-09}, + journal = {Nature Physics}, + author = {Knaster, J. and Moeslang, A. and Muroga, T.}, + month = may, + year = {2016}, + note = {Number: 5 Publisher: Nature Publishing Group}, - pages = {17798}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MBUVUJ3Z\\Delaporte-Mathurin et al. - 2020 - Parametric study of hydrogenic inventory in the IT.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VUYGDUV6\\s41598-020-74844-w.html:text/html}, + pages = {424--434}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\BN5347RZ\\Knaster et al. - 2016 - Materials research for fusion.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5FJW42KL\\nphys3735.html:text/html}, +} + +@article{del_nevo_recent_2019, + series = {{SI}:{SOFT}-30}, + title = {Recent progress in developing a feasible and integrated conceptual design of the {WCLL} {BB} in {EUROfusion} project}, + volume = {146}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379619303503}, + doi = {10.1016/j.fusengdes.2019.03.040}, + abstract = {The water-cooled lithium-lead breeding blanket is in the pre-conceptual design phase. It is a candidate option for European DEMO nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium-lead as breeder-multiplier, pressurized water as coolant and EUROFER as structural material. Current design is based on DEMO 2017 specifications. Two separate water systems are in charge of cooling the first wall and the breeding zone: thermo-dynamic cycle is 295–328 °C at 15.5 MPa. The breeder enters and exits from the breeding zone at 330 °C. Cornerstones of the design are the single module segment approach and the water manifold between the breeding blanket box and the back supporting structure. This plate with a thickness of 100 mm supports the breeding blanket and is attached to the vacuum vessel. It is in charge to withstand the loads due to normal operation and selected postulated initiating events. Rationale and progresses of the design are presented and substantiated by engineering evaluations and analyses. Water and lithium lead manifolds are designed and integrated with the two consistent primary heat transport systems, based on a reliable pressurized water reactor operating experience, and six lithium lead systems. Open issues, areas of research and development needs are finally pointed out.}, + language = {en}, + urldate = {2021-02-08}, + journal = {Fusion Engineering and Design}, + author = {Del Nevo, A. and Arena, P. and Caruso, G. and Chiovaro, P. and Di Maio, P. A. and Eboli, M. and Edemetti, F. and Forgione, N. and Forte, R. and Froio, A. and Giannetti, F. and Di Gironimo, G. and Jiang, K. and Liu, S. and Moro, F. and Mozzillo, R. and Savoldi, L. and Tarallo, A. and Tarantino, M. and Tassone, A. and Utili, M. and Villari, R. and Zanino, R. and Martelli, E.}, + month = sep, + year = {2019}, + keywords = {DEMO, WCLL, EUROfusion, Breeding blanket}, + pages = {1805--1809}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\D5Z7ELJU\\Del Nevo et al. - 2019 - Recent progress in developing a feasible and integ.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YK6Y8ZMV\\S0920379619303503.html:text/html}, +} + +@article{sun_synergistic_2020, + title = {Synergistic effects of high energy helium irradiation and damage introduction at high temperature on hydrogen isotope retention in plasma facing materials}, + volume = {533}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311519313017}, + doi = {10.1016/j.jnucmat.2020.152122}, + abstract = {In this study, energetic helium (He) ion irradiation was performed to obtain bulk He distribution in tungsten (W) materials, concurrent with damage introduction at high temperature. Then, deuterium (D) implantation and thermal desorption spectrometry were performed to evaluate D retention. At the same time, the surface tritium (T) concentration and depth distribution were evaluated by imaging plate (IP) and β-ray induced X-ray spectroscopy (BIXS) measurements after mixed D-T gas exposure. Numerical simulations were applied to evaluate changes in binding energies, diffusion depths, and trapping sites under different irradiation conditions. The results showed that weak trapping sites with higher concentration, such as vacancies, were produced during only energetic He+ irradiation events, leading to enhancement of D retention. Fe3+-He+ simultaneous irradiation promoted the formation of HexVy complexes, which reduced the concentration of vacancy trapping sites and changed the stress field around defects, leading to the suppression of D trapping behavior. From the reduced effects of D retention caused by HexVy complexes at higher temperatures, the results suggested that defect recovery was the dominant mechanism. With increasing damage level at higher temperatures, more weak trapping sites, such as dislocations and vacancies sites, were produced, leading to a more dominant influence on D retention than HexVy complex effects. It was also found that HexVy complexes prevented D diffusion to the bulk and that simulation results showed that the damage level had little impact on D diffusion depth.}, + language = {en}, + urldate = {2020-06-24}, + journal = {Journal of Nuclear Materials}, + author = {Sun, F. and Nakata, M. and Lee, S. E. and Zhao, M. and Wada, T. and Yamazaki, S. and Koike, A. and Kondo, S. and Hinoki, T. and Hara, M. and Oya, Y.}, + month = may, + year = {2020}, + keywords = {Tungsten, TDS, Fusion, Helium, Simulation, Hydrogen isotope, Irradiation damages}, + pages = {152122}, + annote = {He affects the TDS spectrum but not because of trapping INSIDE bubbles. Rather because the He implantation created vacancies (high energy)...}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\H4BAXPEY\\Sun et al. - 2020 - Synergistic effects of high energy helium irradiat.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\3PHR77IB\\S0022311519313017.html:text/html}, } -@article{delaporte-mathurin_influence_2021, - title = {Influence of interface conditions on hydrogen transport studies}, - volume = {61}, - copyright = {All rights reserved}, - issn = {0029-5515}, - url = {http://iopscience.iop.org/article/10.1088/1741-4326/abd95f}, - doi = {10.1088/1741-4326/abd95f}, - abstract = {This work investigates the influence of hydrogen chemical potential continuity across solid material interfaces. The implementation of the mathematical model in FESTIM is verified using the Method of Exact Solutions (MES) and the Method of Manufactured Solutions (MMS) in 1D, 2D, with complex material properties and inhomogeneous temperature fields. A comparison test between FESTIM, TMAP7 and Abaqus codes is also performed and the codes show good agreement. The chemical potential continuity condition has an impact up to 40\% on the outgassing particle flux on {\textbackslash}SI4mm composite slabs (W/Cu and Cu/EUROFER) compared to mobile concentration continuity. A method for rapid identification of materials properties from outgassing flux measurements is given. The influence of chemical potential conservation on monoblock inventory is then studied. It is shown that, for the 1D and 2D ITER divertor monobolocks cases, discrepancies only start to appear after approximately {\textbackslash}SI5e6s of full power.}, +@article{sun_modeling_2020, + title = {Modeling and simulation for surface helium effect on hydrogen isotopes diffusion and trapping/detrapping behavior in plasma facing materials}, + volume = {537}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311519315089}, + doi = {10.1016/j.jnucmat.2020.152227}, + abstract = {In this study, surface helium (He) effect on hydrogen isotopes diffusion and trapping/detrapping behavior was modelled and integrated into the HIDT simulation code. Effective dynamics properties of hydrogen in tungsten including diffusivity, solubility, recycling and diffusion barrier were considered to reflect the influence of He bubbles. Simulation results showed that total hydrogen retention was reduced with the existence of He bubbles near surface, which was consistent with the reported laboratory experimental results. It was found that the most significant influence came from the diffusion barrier induced by He bubbles. With increasing the barrier factor, total hydrogen retention changed from the tendency of decrease to increase. When the barrier factor was less than 0.3, hydrogen desorption from the implantation surface was dominant, while that from the backside surface became dominant when the barrier factor was greater than 0.4. In the meanwhile, more hydrogen accumulated beyond the He bubble layer was observed. These hydrogen atoms occupied not only in trapping sites, but also in lattice sites. Based on these findings, three desorption stages, namely surface desorption, major desorption and backside desorption, could characterize the TDS spectra with different mechanisms. In addition, our findings were further substantiated by the reported experimental data. This study provides a new perspective to reveal the surface He effect on hydrogen isotopes retention behavior in plasma facing materials.}, language = {en}, - number = {3}, - urldate = {2021-01-08}, - journal = {Nuclear Fusion}, - author = {Delaporte-Mathurin, Rémi and Hodille, Etienne and Mougenot, Jonathan and Charles, Yann and Temmerman, Gregory De and Leblond, Floriane and Grisolia, Christian}, - year = {2021}, - pages = {036038}, - file = {Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DT8CVDFY\\Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:application/pdf;IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XWFPUHLX\\Delaporte-Mathurin et al. - 2021 - Influence of interface conditions on hydrogen tran.pdf:application/pdf}, + urldate = {2020-08-31}, + journal = {Journal of Nuclear Materials}, + author = {Sun, F. and Li, X. C. and Zhang, L. and Nakata, M. and Zhao, M. and Wada, T. and Yamazaki, S. and Koike, A. and Oya, Y.}, + month = aug, + year = {2020}, + keywords = {Tungsten, TDS, Fusion, Helium bubble, Diffusion barrier, Hydrogen retention, Modeling and simulation}, + pages = {152227}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\8AAFSH5I\\S0022311519315089.html:text/html}, } -@article{nicholas_re-examining_2021, - title = {Re-examining the role of nuclear fusion in a renewables-based energy mix}, - volume = {149}, - issn = {0301-4215}, - url = {http://www.sciencedirect.com/science/article/pii/S0301421520307540}, - doi = {10.1016/j.enpol.2020.112043}, - abstract = {Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineering and materials science will still impose significant constraints on the characteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the significant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fusion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation.}, +@article{ialovega_hydrogen_2020, + title = {Hydrogen trapping in tungsten: impact of helium irradiation and thermal cycling}, + volume = {T171}, + issn = {1402-4896}, + shorttitle = {Hydrogen trapping in tungsten}, + url = {https://doi.org/10.1088%2F1402-4896%2Fab68bd}, + doi = {10.1088/1402-4896/ab68bd}, + abstract = {The impact of helium (He) plasma exposure with He fluxes relevant for ITER and WEST on the near-surface microstructure of polycrystalline tungsten (W) is investigated by coupling transmission electron microscopy (TEM) analysis and thermal desorption spectrometry (TDS) measurements. The samples were exposed in the PSI-2 linear plasma device to 75 eV He ions up to the fluence of 3 × 1023 He m−2 with the surface temperature in the range 1053–1073 K. The obtained He bubbles–enriched W samples are subsequently probed with sequences of low flux and low fluence 250 eV deuterium (D) ion implantations and TDS measurements in an ultra-high-vacuum setup to study the effects of the near-surface morphology changes due to the helium irradiation on fundamental mechanisms of deuterium retention. The results obtained for two different near-surface layer He bubbles morphologies revealed that the effects of He irradiation on D retention in W strongly depend on its subsequent thermal cycling. For annealing below 900 K, deuterium retention is similar to the one measured in pristine W. In contrast, for annealing above 1150 K, deuterium retention in the He bubbles-enriched W is increased 3–8 fold as compared to non-damaged W. Additionally, the deuterium desorption peak shifts from 540 to 450 K. This increase of D trapping in the He bubbles-enriched W annealed above 1150 K is presumably associated with a modification of the near-surface microstructure concurrent with an outgassing of He.}, language = {en}, - urldate = {2021-01-06}, - journal = {Energy Policy}, - author = {Nicholas, T. E. G. and Davis, T. P. and Federici, F. and Leland, J. and Patel, B. S. and Vincent, C. and Ward, S. H.}, - month = feb, - year = {2021}, - keywords = {Fusion, Decarbonisation, EROI, Firm resources, Load-following, Nuclear, Perceptions, Waste}, - pages = {112043}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\M4HEEKWE\\S0301421520307540.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JMMM75FH\\Nicholas et al. - 2021 - Re-examining the role of nuclear fusion in a renew.pdf:application/pdf}, + urldate = {2020-05-27}, + journal = {Physica Scripta}, + author = {Ialovega, Mykola and Bernard, Elodie and Bisson, Régis and Martin, Celine and Sakamoto, Ryuichi and Kreter, Arkadi and Hodille, Etienne and Angot, Thierry and Grisolia, Christian}, + month = jan, + year = {2020}, + note = {Publisher: IOP Publishing}, + keywords = {TDS}, + pages = {014066}, + file = {Ialovega et al. - 2020 - Hydrogen trapping in tungsten impact of helium ir.pdf:D\:\\Logiciels\\data_zotero\\storage\\LZLBYNB8\\Ialovega et al. - 2020 - Hydrogen trapping in tungsten impact of helium ir.pdf:application/pdf}, } -@article{zhang_integrated_2010, - series = {Proceedings of the {Ninth} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, - title = {Integrated simulation of tritium permeation in solid breeder blankets}, - volume = {85}, +@article{zhao_tritium_2019, + title = {Tritium transport analysis for {WCCB} blanket of {CFETR} based on {COMSOL}}, + volume = {140}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379610002309}, - doi = {10.1016/j.fusengdes.2010.05.018}, - abstract = {Numerical simulation of co-permeation of tritium and hydrogen from breeding zones to the coolant in the helium cooled pebble-bed blanket is performed in this paper. 3D multi-species convection–diffusion models integrated with thermal-fluid analysis in porous media are assessed and then used to estimate the associated tritium permeation for a solid breeder blanket module. Benchmark calculations give a reasonable agreement on the co-permeation rates with the experimental data. Simulation in a TBM unit show that purge gas flow can strongly affect tritium transport, increasing the purge flow velocity is an effective method to reduce tritium permeation to the coolant. In the case where hydrogen is added to the purge gas stream to promote tritium release, the co-permeation of H2, T2, and HT are taken into account in the permeation simulation, results show that permeation flux of T–T molecules is reduced due to the effect of co-permeation of hydrogen.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379619300523}, + doi = {10.1016/j.fusengdes.2019.01.044}, + abstract = {As for the fusion reactor, tritium has received widely attention due to its self-sufficiency and its influence on the safe operation of the fusion reactor. As a result, quantitative analysis of tritium diffusion, inventory, permeation in the blanket is crucial to the design of tritium fuel circulating system and safety issue. In this study, a two-dimensional model for tritium transport in water cooled ceramic breeder (WCCB) blanket is created, and finite element software COMSOL is used to simulate the tritium transport process. The amount of tritium inventory, the tritium permeation into the coolant, the tritium taken by purge gas and the tritium release are calculated. Besides, the concentration profile of tritium and temperature profile in the blanket are given as well as the sensitivity analysis about the velocity of purge gas is conducted which can offer a reference for the design of tritium extraction system.}, language = {en}, - number = {10}, - urldate = {2021-01-12}, + urldate = {2021-02-06}, journal = {Fusion Engineering and Design}, - author = {Zhang, Hongjie and Ying, Alice and Abdou, Mohamed A.}, - month = dec, - year = {2010}, - keywords = {Tritium permeation, Breeding blanket, 3D Model, Purge convection}, - pages = {1711--1715}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\P2BH9CFH\\Zhang et al. - 2010 - Integrated simulation of tritium permeation in sol.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\734QWLQ9\\S0920379610002309.html:text/html}, + author = {Zhao, Xueli and Zhang, Bing and Chen, Lei and Huang, Kai and Liu, Songlin}, + month = mar, + year = {2019}, + keywords = {COMSOL, Tritium permeation, Tritium inventory, Tritium release, WCCB blanket}, + pages = {1--10}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HG87497B\\Zhao et al. - 2019 - Tritium transport analysis for WCCB blanket of CFE.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PIZNZEA4\\S0920379619300523.html:text/html}, } -@article{pasler_development_2018, - title = {Development and verification of a component-level hydrogen transport model for a {DEMO}-like {HCPB} breeder unit with {OpenFOAM}}, - volume = {127}, +@article{zhao_3d_2020, + title = {{3D} tritium transport analysis for {WCCB} blanket based on {COMSOL}}, + volume = {151}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618300103}, - doi = {10.1016/j.fusengdes.2018.01.008}, - abstract = {This work describes the development of a numerical model to simulate transient tritium transport on the breeder unit (BU) level for the EU helium cooled pebble bed (HCPB) concept for DEMO. The key output quantities of the model are the tritium concentration in the purge gas and in the coolant and the tritium inventory inside the BU structure. The model capabilities should cover normal operation as well as accident conditions. The Open Source Field Operation And Manipulation framework OpenFOAM serves as the basis for the model. Equations and boundary conditions required for hydrogen isotopes transport are implemented. Realistic properties data as diffusion constants and Sieverts constants are required, too. A key model issue is solid-fluid interface mass transfer. Two correlations that (1) approaches Sieverts equilibrium in the diffusion limit and (2) a rate dependent correlation that includes the diffusion limit for very high ad-/desorption rate constants are introduced. A two species interface mass transfer correlation based on the single species rate dependent correlation is developed, too. First verification calculations are compared to analytic solutions and TMAP calculations.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379619309019}, + doi = {10.1016/j.fusengdes.2019.111405}, + abstract = {As one of the CFETR candidate blanket schemes, Water-Cooled Ceramic Breeder (WCCB) blanket is being designed and developed by Institute of Plasma Physics, Chinese Academy of Sciences. Considering the safe operation of blanket, especially the radioactivity of tritium, it is crucial to study the tritium performance in the blanket, such as inventory, permeation, tritium taken by purge gas and release, which can likewise provide information for study and design of Tritium Extraction System (TES) and Coolant Purification System (CPS). Based on Finite Element Method (FEM), a more accurate three-dimensional model is set up using COMSOL Multi-physics. The influence of temperature distribution and velocity field of breeder zones on tritium transport is considered in the modelling. Finally, the tritium inventory, tritium permeation, tritium taken by purge gas and tritium release out of the blanket are calculated as well as the sensitivity analysis is conducted.}, language = {en}, - urldate = {2021-01-12}, + urldate = {2021-02-06}, journal = {Fusion Engineering and Design}, - author = {Pasler, Volker and Arbeiter, Frederik and Klein, Christine and Klimenko, Dmitry and Schlindwein, Georg and von der Weth, Axel}, + author = {Zhao, Xueli and Ni, Muyi and Nie, Baojie and Zhang, Bing and Chen, Lei and Huang, Kai and Liu, Songlin}, month = feb, - year = {2018}, - keywords = {Tritium transport, Safety, HCPB, OpenFOAM}, - pages = {249--258}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JNTLMS9Z\\Pasler et al. - 2018 - Development and verification of a component-level .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\V7V35MRT\\S0920379618300103.html:text/html}, + year = {2020}, + keywords = {COMSOL, Tritium permeation, Tritium inventory, Tritium release, WCCB blanket, 3D model}, + pages = {111405}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\NYFZAL5G\\Zhao et al. - 2020 - 3D tritium transport analysis for WCCB blanket bas.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\DMIGJLU9\\S0920379619309019.html:text/html}, } -@article{ying_breeding_2018, - series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, - title = {Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation: {A} {MATLAB}/{Simulink}, {COMSOL} integrated dynamic tritium transport model for {HCCR} {TBS}}, - volume = {136}, +@article{zinkle_operating_2000, + title = {Operating temperature windows for fusion reactor structural materials}, + volume = {51-52}, issn = {0920-3796}, - shorttitle = {Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379618303879}, - doi = {10.1016/j.fusengdes.2018.04.093}, - abstract = {An integrated, multi-physics, dynamic predictive tool to quantify tritium retention, removal, and permeation for HCCR Test Blanket System (TBS) is presented in this paper. The tool expands from detailed COMSOL component models developed previously at UCLA, into an integrated, system-level blanket model using MATLAB/Simulink. It aims at achieving self-consistent predictions in particular concerning dynamic tritium concentration built-up in the He coolant. The integration is achieved by implementing COMSOL component models in the discrete section of Simulink S-Functions. The model replicates HCCR TBS process flow diagram and preserves main tritium flow characteristics for both helium cooling and tritium extraction systems. Current results demonstrate importance of detailed component models as well as dynamic simulation for improved accuracy on answers to questions related to safety/licensing and designs.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379600003203}, + doi = {10.1016/S0920-3796(00)00320-3}, + abstract = {A critical analysis is presented of the operating temperature windows for nine candidate fusion reactor structural materials: four reduced-activation structural materials (oxide-dispersion-strengthened and ferritic/martensitic steels containing 8–12\%Cr, V–4Cr–4Ti, and SiC/SiC composites), copper-base alloys (CuNiBe), tantalum-base alloys (e.g. Ta–8W–2Hf), niobium alloys (Nb–1Zr), and molybdenum and tungsten alloys. The results are compared with the operating temperature limits for Type 316 austenitic stainless steel. Several factors define the allowable operating temperature window for structural alloys in a fusion reactor. The lower operating temperature limit in all body-centered cubic (BCC) and most face-centered cubic (FCC) alloys is determined by radiation embrittlement (decrease in fracture toughness), which is generally most pronounced for irradiation temperatures below ∼0.3 TM where TM is the melting temperature. The lower operating temperature limit for SiC/SiC composites will likely be determined by radiation-induced thermal conductivity degradation, which becomes more pronounced in ceramics with decreasing temperature. The upper operating temperature limit of structural materials is determined by one of four factors, all of which become more pronounced with increasing exposure time: (1) thermal creep (grain boundary sliding or matrix diffusional creep); (2) high temperature He embrittlement of grain boundaries; (3) cavity swelling (particularly important for SiC and Cu alloys); or (4) coolant compatibility/corrosion issues. In many cases, the upper temperature limit will be determined by coolant corrosion/compatibility rather than by thermal creep or radiation effects. The compatibility of the structural materials with Li, Pb–Li, Sn–Li, He and Flibe (Li2BeF4) coolants is summarized.}, language = {en}, - urldate = {2021-01-12}, + urldate = {2021-02-05}, journal = {Fusion Engineering and Design}, - author = {Ying, Alice and Zhang, Hongjie and Merrill, Brad and Ahn, Mu-Young and Cho, Seungyon}, + author = {Zinkle, S. J and Ghoniem, N. M}, month = nov, - year = {2018}, - keywords = {Test blanket system, COMSOL, Simulink, Tritium transport and permeation modeling}, - pages = {1153--1160}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LWMJN9U5\\Ying et al. - 2018 - Breeding blanket system design implications on tri.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4TB27JJN\\S0920379618303879.html:text/html}, -} - -@article{charles_effect_2021, - title = {Effect of transient trapping on hydrogen transport near a blunting crack tip}, - issn = {0360-3199}, - url = {http://www.sciencedirect.com/science/article/pii/S036031992034787X}, - doi = {10.1016/j.ijhydene.2020.12.155}, - abstract = {The paper revisits the way transient trapping is introduced in the literature based on the Sofronis and McMeeking model (Sofronis and McMeeking, 1989) [1] of hydrogen transport. It is shown that the direct use of the improved formulation made by Krom et al. (1999) [2] for transient trapping may lead to non-physical results of hydrogen concentration in case of an insulated system. The use of McNabb and Foster trapping kinetic equation is more relevant, and its ability to model both trap creation and kinetic trapping is investigated on a Small Scale Yielding configuration for the sake of comparison with a reference case from the literature. A parametric study is conducted, exhibiting differences with literature, and emphasizes on the significant effect of trapping kinetics on the hydrogen distribution.}, - language = {en}, - urldate = {2021-01-12}, - journal = {International Journal of Hydrogen Energy}, - author = {Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, - month = jan, - year = {2021}, - keywords = {Diffusion, Abaqus, Hydrogen trapping, Crack tip plasticity, Finite elements}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YR9K4J6Y\\S036031992034787X.html:text/html}, + year = {2000}, + keywords = {Structural materials, Fusion energy applications, Temperature windows}, + pages = {55--71}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\J4MF3KJW\\Zinkle et Ghoniem - 2000 - Operating temperature windows for fusion reactor s.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NZU3HQZ9\\S0920379600003203.html:text/html}, } -@article{candido_tritium_2019, - series = {{SI}:{SOFT}-30}, - title = {Tritium transport model at breeder unit level for {WCLL} breeding blanket}, - volume = {146}, +@article{gabriel_2d_2007, + series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, + title = {A {2D} finite element modelling of tritium permeation for the {HCLL} {DEMO} blanket module}, + volume = {82}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379619302170}, - doi = {10.1016/j.fusengdes.2019.02.041}, - abstract = {In a fusion power demonstration plant (DEMO), the development of a tritium transport model is mandatory in order to correctly predict the tritium concentration inside the liquid metal, the permeated flux through the structural materials and into the coolant, playing a fundamental role in guaranteeing tritium self-sufficiency in the fusion reactor and safety both for the workers and for the external environment. In the present work, a multi-physics 3D tritium transport model has been assessed for a single breeder unit located in the outboard equatorial module of the Water-Cooled Lithium Lead (WCLL) breeding blanket of DEMO, adopting an approach that permits to have a modelling tool able to be adaptive within certain margins to changes in operating parameters and geometry. The transport has been modelled considering advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel (adsorption/desorption), diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant (recombination/dissociation), advection-diffusion of diatomic tritium into the coolant. The effect of buoyancy forces, which arise due to temperature variation, has been also considered. Under the above-specified phenomena, tritium concentrations, inventories and losses have been derived.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379607004061}, + doi = {10.1016/j.fusengdes.2007.08.001}, + abstract = {A local finite element modelling of the tritium permeation through the HCLL breeder unit cooling plates is presented. The tritium concentration in the helium and in the lithium lead are evaluated by solving partial differential equations governing the tritium balance, the thermal field and the lithium lead velocity field in a simplified 2D-geometrical representation of the breeder unit at the mid-equatorial plan. Using a factorial design at two levels as numerical experiments it is shown that the magnetic field and the natural convection are not relevant for the estimation of the permeation. Moreover, numerical analyses showed a developed concentration boundary layer acting as a mass transfer resistance which is equivalent to a PRF of 30.}, language = {en}, - urldate = {2021-01-12}, + number = {15}, + urldate = {2021-02-05}, journal = {Fusion Engineering and Design}, - author = {Candido, Luigi and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, - month = sep, - year = {2019}, - keywords = {Tritium transport, DEMO, Breeding blanket, WCLL, Buoyancy effect}, - pages = {1207--1210}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G5RUYKPC\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8BDBXJIG\\S0920379619302170.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\N6WWPB59\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RR3LV77Y\\S0920379619302170.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KB3HXFIA\\Candido et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf}, + author = {Gabriel, F. and Escuriol, Y. and Dabbene, F. and Gastaldi, O. and Salavy, J. F. and Giancarli, L.}, + month = oct, + year = {2007}, + keywords = {MHD, Tritium permeation, Fusion reactor blanket, Mixed convection}, + pages = {2204--2211}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4U4BT4VN\\Gabriel et al. - 2007 - A 2D finite element modelling of tritium permeatio.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SA8AISTK\\S0920379607004061.html:text/html}, } -@article{alberghi_magneto-convective_2020, - title = {Magneto-convective effect on tritium transport at breeder unit level for the {WCLL} breeding blanket of {DEMO}}, - volume = {160}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620305445}, - doi = {10.1016/j.fusengdes.2020.111996}, - abstract = {The Water-Cooled Lithium-Lead (WCLL) is one of the four breeding blanket concepts proposed by Europe in view of its DEMO reactor. The velocity field of the electrically conducting lead-lithium eutectic alloy inside the blanket is strongly influenced by the external magnetic field used for plasma confinement combined with buoyancy effect. The strength of the magnetohydrodynamics (MHD) effect and of the magneto-convective effect (MHD and buoyancy force) depends on the intensity of the magnetic field and its orientation with respect to the direction of the lead-lithium motion. This phenomenon significantly influences the resulting temperature and velocity fields, and therefore the tritium transport inside the breeding blanket. A multi-physics approach of a 3D tritium transport model is presented for a simplified geometry of the WCLL breeding blanket. In particular, advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel, diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant, and advection-diffusion of diatomic tritium into the coolant, temperature field, velocity fields of both lead-lithium and water, buoyancy forces, and MHD effect have been included in this study. The tritium concentrations and the inventories inside the lead-lithium, in the Eurofer pipes and in the baffle, and in the water coolant have been evaluated.}, +@article{abdou_physics_2020, + title = {Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency}, + volume = {61}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/abbf35/meta}, + doi = {10.1088/1741-4326/abbf35}, language = {en}, - urldate = {2021-01-12}, - journal = {Fusion Engineering and Design}, - author = {Alberghi, Ciro and Candido, Luigi and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, + number = {1}, + urldate = {2021-02-05}, + journal = {Nuclear Fusion}, + author = {Abdou, Mohamed and Riva, Marco and Ying, Alice and Day, Christian and Loarte, Alberto and Baylor, L. R. and Humrickhouse, Paul and Fuerst, Thomas F. and Cho, Seungyon}, month = nov, year = {2020}, - keywords = {Tritium transport, DEMO, Breeding blanket, WCLL, Buoyancy forces, Magneto-convection, MHD}, - pages = {111996}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RMI3A2WW\\S0920379620305445.html:text/html;Alberghi et al. - 2020 - Magneto-convective effect on tritium transport at .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6Z2ZTL2I\\Alberghi et al. - 2020 - Magneto-convective effect on tritium transport at .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MYAUY4V4\\S0920379620305445.html:text/html}, + note = {Publisher: IOP Publishing}, + pages = {013001}, + file = {Abdou et al. - 2020 - Physics and technology considerations for the deut.pdf:D\:\\Logiciels\\data_zotero\\storage\\YM2TGZPV\\Abdou et al. - 2020 - Physics and technology considerations for the deut.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\H77WYVLR\\abbf35.html:text/html}, } -@article{candido_integrated_2020, - title = {An integrated hydrogen isotopes transport model for the {TRIEX}-{II} facility}, - volume = {155}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620301332}, - doi = {10.1016/j.fusengdes.2020.111585}, - abstract = {At ENEA Brasimone Research Centre, Italy, a new experimental facility named TRIEX-II (Tritium Extraction) was designed and installed. Its aim is to characterize, in the range of operating conditions foreseen for the European Test Blanket System WCLL-TBS, several extraction technologies for hydrogen isotopes (Q2) solubilized in the flowing metallic LiPb alloy (15.7 at. \% Li). One of these technologies is the packed column, an example of Gas/Liquid Contactors (GLCs). This paper proposes a multiscale modelling tool, combining different scales through two computational tools. The extraction column mock-up is described by a component-detail level model, developed in COMSOL Multiphysics, and integrated into a system level code of the whole TRIEX-II circuit, developed using MATLAB/Simulink. The integration is carried out by implementing the COMSOL component into an S-function of MATLAB/Simulink, preserving the process flow diagram of the loop. In this way, it was possible to quantify the Q2 concentrations and the permeation fluxes, and to evaluate the theoretical extraction efficiency. The LiPb flow field inside the extractor was also derived. Finally, a comparison with the experimental results was performed. The results suggest that this tool could be adapted for analyses of complex systems, at a multiscale level, in view of design improvements and safety studies for the tritium cycle of ITER.}, +@article{gao_coupled_2018, + title = {A coupled rate theory-{Monte} {Carlo} model of helium bubble evolution in plasma-facing micro-engineered tungsten}, + volume = {509}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311518302095}, + doi = {10.1016/j.jnucmat.2018.04.051}, + abstract = {A multiscale model of helium bubble evolution in plasma-facing materials is developed. The model links different stages of helium bubble evolution: deposition, nucleation, growth, motion, and coalescence. Helium deposition is simulated with the SRIM Monte Carlo program to give spatial information on helium and displacement damage distributions near the surface. This deposition profile is then introduced into a space-dependent rate theory of bubble nucleation and growth to describe the early stages of the distribution and size of helium bubbles. The coarsening stage of bubble evolution as a result of whole bubble motion, interaction, and coalescence is modeled by a new Object Kinetic Monte Carlo (OKMC) model, for which initial conditions are taken from the mean-field rate theory calculations. The model is compared to experimental data on low-energy helium plasma interaction with micro-engineered tungsten (W), and on high-energy helium ion deposition in flat W samples. Novel features of the multiscale model include: (1) space-dependent rate theory; (2) OKMC model of bubble motion in stress and temperature fields; and (3) application of the model to micro-engineered materials, and comparison with experiments on the same time-scale. At low helium ion energy, it is found that the mechanism of trap mutation is essential in achieving good agreement with experimental measurements. On the other hand, good agreement with experiments at high incident ion energy and temperature showed the importance of bubble coalescence and coarsening as main mechanisms. The results of the model are compared with experiments on flat W surfaces irradiated at high ion energy (30 keV), and with micro-engineered W, where the surface is coated with high-density micro-pillars at low ion energy (around 100 eV). The predicted average bubble radius and density are in qualitative agreement with experimental results.}, language = {en}, - urldate = {2021-01-12}, - journal = {Fusion Engineering and Design}, - author = {Candido, Luigi and Cantore, Mattia and Galli, Edoardo and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, - month = jun, - year = {2020}, - keywords = {WCLL, COMSOL, GLC, Multiscale, TRIEX-II, Tritium modelling}, - pages = {111585}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XIJF7PU5\\Candido et al. - 2020 - An integrated hydrogen isotopes transport model fo.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2X54R6B5\\S0920379620301332.html:text/html}, + urldate = {2020-07-22}, + journal = {Journal of Nuclear Materials}, + author = {Gao, Edward and Ghoniem, Nasr M.}, + month = oct, + year = {2018}, + pages = {577--590}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\XP59YFBL\\Gao et Ghoniem - 2018 - A coupled rate theory-Monte Carlo model of helium .pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\WLD8DL4X\\Gao et Ghoniem - 2018 - A coupled rate theory-Monte Carlo model of helium .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\HVGW2HM4\\S0022311518302095.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\G4T5QSLT\\S0022311518302095.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PRDQJNAC\\S0022311518302095.html:text/html}, } -@article{li_development_2020, - title = {Development of tritium dynamic transport analysis tool for tritium breeding blanket system using {Modelica}}, - volume = {161}, +@article{wei_shape_2010, + title = {The shape of bubbles in {He}-implanted {Cu} and {Au}}, + volume = {63}, + issn = {1359-6462}, + url = {http://www.sciencedirect.com/science/article/pii/S135964621000299X}, + doi = {10.1016/j.scriptamat.2010.04.043}, + abstract = {Bubble evolution under thermal annealing has been studied in He-implanted Cu and Au by in situ transmission electron microscopy. We show that, under the minimum energy requirement of system, the bubble developed into an octahedron (or truncated octahedron) shape consisting of \{111\} planes in the manner predicted by the Wulff construction. The non-spherical shape of the bubbles and the existence of sessile dislocations along the edges of octahedron provide a barrier to Ostwald ripening and migration of bubbles, leading to low bubble mobility under thermal annealing.}, + language = {en}, + number = {4}, + urldate = {2021-01-30}, + journal = {Scripta Materialia}, + author = {Wei, Qiangmin and Li, Nan and Sun, Kai and Wang, L. M.}, + month = aug, + year = {2010}, + keywords = {Annealing, Copper, Implantation, Transmission electron microscopy (TEM)}, + pages = {430--433}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\C8BDLF7T\\Wei et al. - 2010 - The shape of bubbles in He-implanted Cu and Au.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NWTPCXSV\\S135964621000299X.html:text/html}, +} + +@article{pick_model_1985, + title = {A model for atomic hydrogen-metal interactions — application to recycling, recombination and permeation}, + volume = {131}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/0022311585904593}, + doi = {10.1016/0022-3115(85)90459-3}, + abstract = {A model for the interaction of hydrogen with metals is discussed which includes the surface concentration and the surface potential and is based on the observation that molecular hydrogen is dissociated before it is chemisorbed at a metal surface. It is shown that an activation barrier for dissociation of molecular hydrogen at the metal surface leads to an enhanced solubility and increased permeation rate of hydrogen in a metal exposed to atomic hydrogen as compared to molecular hydrogen. The sticking probability of molecular hydrogen on clean transition metals has been measured in the past and shown to be of the order of unity. As no activation barrier is present no difference is expected between atomic and molecular hydrogen. Whenever large differences have been observed in the past they must be attributed to an impurity contamination of the metal surface. Substantial reductions of the sticking probability due to dissociation barriers have been found for metals contaminated with less than one monolayer of electronegative impurities. We compare our model with earlier descriptions of hydrogen metal interactions. A theoretical expression is derived for the “recombination rate constant”. Furthermore we discuss implications of our model on hydrogen permeation (“super permeation”) as well as hydrogen pumping and pumping panels in tokamaks.}, + language = {en}, + number = {2}, + urldate = {2021-01-26}, + journal = {Journal of Nuclear Materials}, + author = {Pick, M. A. and Sonnenberg, K.}, + month = apr, + year = {1985}, + pages = {208--220}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\FTWVWFIG\\0022311585904593.html:text/html}, +} + +@article{vizvary_european_2020, + title = {European {DEMO} first wall shaping and limiters design and analysis status}, + volume = {158}, issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620305718}, - doi = {10.1016/j.fusengdes.2020.112023}, - abstract = {Demonstration of the engineering feasibility of tritium breeding, including tritium generation, tritium extraction, tritium control and tritium safety is one of the main objectives of ITER Testing Blanket Module (TBM) Program. As one of TBM concepts, the tritium transport assessment of the China Helium Cooled Ceramic Breeder TBM and its ancillary systems (called test blanket system, TBS) is absolutely vital to understand and analyze the dynamic tritium behaviors in the system in detail according to the ITER operation scenario. Considering the requirements of the tritium transport analysis for the HCCB TBS, an integrated dynamic tritium transport analysis tool has been developed by the system simulation language “Modelica”. The multiple dynamic physics effects are considered in the tool, including the aspects impacting the tritium transport, simplified thermal-hydraulics considering only the linear loss and local loss in fluid, 1-d thermal conduction in solid, hydrogen isotope transport in fluid, 1-d tritium permeation in solid, tritium solution and recombination on solid surfaces, tritium desorption from ceramic breeder etc. A simplified model of the HCCB TBS is modeled to verify the functions and accuracy of this tool. The results, such as dynamic change of tritium concentration/partial pressure in fluids, dynamic change of tritium inventory in solids, tritium permeation fluxes etc., have been obtained, which are preliminary verified at various aspects by comparing with analytical and hand calculations.}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379620302246}, + doi = {10.1016/j.fusengdes.2020.111676}, + abstract = {The anticipated heat flux limit of the European DEMO first wall is ∼1−2 MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected. This involves dedicated discrete limiters in certain regions of the machine that would take the brunt of the heat load as well as adequate shaping of the first wall. The current concept envisages limiters at a few (3–4) equatorial ports to cope with the ramp-up of the plasma; upper limiters (in ∼8 upper ports) are considered for upward vertical displacement events. Two design options have been considered for these limiters: a modular design where the limiter plasma facing components are attached to individual plates that are assembled together so that transient electromagnetic loads can be reduced, and in case of damage the plates can be replaced/repaired individually; and a divertor-like design where the plasma facing components are attached to a single Eurofer cassette. Other limiters considered include inner wall limiters in case of plasma contraction and lower limiters may be needed for downward vertical displacement events. The thermal hydraulic finite element analysis results show that the integrity of the cooling pipes can be maintained during the anticipated transient events. The limiters are considered to be sacrificial and designed to be replaceable independently from the breeding blanket system. The design has to allow that installation, removal or replacement of the limiters can be performed remotely. Strategy to tackle outstanding issues and required R\&D is also discussed.}, language = {en}, - urldate = {2021-01-12}, + urldate = {2021-01-25}, journal = {Fusion Engineering and Design}, - author = {Li, Ruyan and Wang, Xiaoyu and Zhang, Long and Wang, Jun}, - month = dec, + author = {Vizvary, Z. and Arter, W. and Bachmann, C. and Barrett, T. R. and Chuilon, B. and Cooper, P. and Flynn, E. and Firdaouss, M. and Franke, T. and Gerardin, J. and Gowland, R. and Kovari, M. and Maviglia, F. and Richiusa, M. L. and Adame, E. V. Rosa and Vorpahl, C. and Wilde, A. and Xue, Y.}, + month = sep, year = {2020}, - keywords = {Dynamic tritium transport, HCCB TBS, Modelica}, - pages = {112023}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MMBF3MLB\\Li et al. - 2020 - Development of tritium dynamic transport analysis .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GT6VJMZ2\\S0920379620305718.html:text/html}, + keywords = {DEMO, First Wall shaping, Limiter, PFC, Thermo-hydraulic analysis}, + pages = {111676}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YLGQCQT5\\Vizvary et al. - 2020 - European DEMO first wall shaping and limiters desi.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2PYYULC8\\S0920379620302246.html:text/html}, } -@article{urgorri_tritium_2017, - title = {Tritium transport modeling at system level for the {EUROfusion} dual coolant lithium-lead breeding blanket}, - volume = {57}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/aa7f9d}, - doi = {10.1088/1741-4326/aa7f9d}, - abstract = {The dual coolant lithium lead (DCLL) breeding blanket is one of the four breeder blanket concepts under consideration within the framework of EUROfusion consortium activities. The aim of this work is to develop a model that can dynamically track tritium concentrations and fluxes along each part of the DCLL blanket and the ancillary systems associated to it at any time. Because of tritium nature, the phenomena of diffusion, dissociation, recombination and solubilisation have been modeled in order to describe the interaction between the lead-lithium channels, the structural material, the flow channel inserts and the helium channels that are present in the breeding blanket. Results have been obtained for a pulsed generation scenario for DEMO. The tritium inventory in different parts of the blanket, the permeation rates from the breeder to the secondary coolant and the amount of tritium extracted from the lead-lithium loop have been computed. Results present an oscillating behavior around mean values. The obtained average permeation rate from the liquid metal to the helium is 1.66 mg while the mean tritium inventory in the whole system is 417 mg. Besides the reference case results, parametric studies of the lead-lithium mass flow rate, the tritium extraction efficiency and the tritium solubility in lead-lithium have been performed showing the reaction of the system to the variation of these parameters.}, +@article{shimwell_paramak_2021, + title = {The {Paramak}: automated parametric geometry construction for fusion reactor designs.}, + volume = {10}, + copyright = {All rights reserved}, + issn = {2046-1402}, + shorttitle = {The {Paramak}}, + url = {https://f1000research.com/articles/10-27/v1}, + doi = {10.12688/f1000research.28224.1}, + abstract = {During the conceptual design process of fusion reactors it is useful to rapidly prototype different design concepts and assess their suitability against a range of high level requirements. Rapid prototyping allows the 'fail early' mantra of other fields to be applied to engineering design. + Furthermore, the rapid generation of low fidelity analysis allows fast exploration of design space, which enables better decisions to be made during concept selection and the detailed design phase. The Paramak is an open-source tool that aims to provide automated parameter driven 3D CAD models for fusion reactor components and magnetic fusion reactors. The geometry produced is compatible with several analysis workflows and this allows iterative automated model building and analysis to help steer the design concept optimisation process. The Paramak uses CadQuery 2 to create the 3D CAD model. The Paramak framework is used to create a few example reactor configurations including: a spherical reactor, a regular large radius tokamak and a compact submersion tank reactor. Input parameters for the various reactors that the Paramak can generate generally fall into three categories: continuous ranges such as blanket thickness, integer ranges such as number of toroidal field coils and categorical parameters such as type of divertor. The Paramak facilitates parameter studies where users can investigate the impact of input design parameters on the reactor performance. The use of modern software practices allows the geometry to be continuously tested in analysis workflows to ensure it is fit for purpose. The generation of output metrics from input parameters lends itself to the use of data science and machine learning approaches in order to steer the design. The Paramak provides rapid construction of analysis ready CAD in a manner that allows the designer to save time when exploring the design space for design studies and facilitate automated generative design.}, language = {en}, - number = {11}, - urldate = {2021-01-12}, - journal = {Nuclear Fusion}, - author = {Urgorri, F. R. and Moreno, C. and Carella, E. and Rapisarda, D. and Fernández-Berceruelo, I. and Palermo, I. and Ibarra, A.}, - month = aug, - year = {2017}, - note = {Publisher: IOP Publishing}, - pages = {116045}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\E7E993WC\\Urgorri et al. - 2017 - Tritium transport modeling at system level for the.pdf:application/pdf}, + urldate = {2021-01-18}, + journal = {F1000Research}, + author = {Shimwell, Jonathan and Billingsley, John and Delaporte-Mathurin, Rémi and Morbey, Declan and Bluteau, Matthew and Shriwise, Patrick and Davis, Andrew}, + month = jan, + year = {2021}, + pages = {27}, + file = {Shimwell et al. - 2021 - The Paramak automated parametric geometry constru.pdf:D\:\\Logiciels\\data_zotero\\storage\\U5RQK6W4\\Shimwell et al. - 2021 - The Paramak automated parametric geometry constru.pdf:application/pdf}, } -@article{spagnuolo_multi-physics_2019, - title = {A multi-physics integrated approach to breeding blanket modelling and design}, - volume = {143}, - issn = {09203796}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379619304648}, - doi = {10.1016/j.fusengdes.2019.03.131}, - language = {en}, - urldate = {2021-01-12}, - journal = {Fusion Engineering and Design}, - author = {Spagnuolo, Gandolfo Alessandro and Chiovaro, Pierluigi and Di Maio, Pietro Alessandro and Favetti, Riccardo}, - month = jun, - year = {2019}, - pages = {35--40}, - file = {Spagnuolo et al. - 2019 - A multi-physics integrated approach to breeding bl.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X9QTMGK2\\Spagnuolo et al. - 2019 - A multi-physics integrated approach to breeding bl.pdf:application/pdf}, +@book{smith_abaqusstandard_2009, + title = {{ABAQUS}/{Standard} {User}'s {Manual}, {Version} 6.9}, + url = {https://www.research.manchester.ac.uk/portal/en/publications/abaqusstandard-users-manual-version-69(0b112d0e-5eba-4b7f-9768-cfe1d818872e).html}, + language = {English}, + urldate = {2020-10-09}, + author = {Smith, Michael}, + year = {2009}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\B7Q393PQ\\abaqusstandard-users-manual-version-69(0b112d0e-5eba-4b7f-9768-cfe1d818872e).html:text/html}, } -@article{ying_advancement_2016, - series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, - title = {Advancement in tritium transport simulations for solid breeding blanket system}, - volume = {109-111}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379615303719}, - doi = {10.1016/j.fusengdes.2015.11.040}, - abstract = {In this paper, advancement on tritium transport simulations was demonstrated for a solid breeder blanket HCCR TBS, where multi-physics and detailed engineering descriptions are considered using a commercial simulation code. The physics involved includes compressible purge gas fluid flow, heat transfer, chemical reaction, isotope swamping effect, and tritium isotopes mass transport. The strategy adopted here is to develop numerical procedures and techniques that allow critical details of material, geometric and operational heterogeneity in a most complete engineering description of the TBS being incorporated into the simulation. Our application focuses on the transient assessment in view of ITER being pulsed operations. An immediate advantage is a more realistic predictive and design analysis tool accounting pulsed operations induced temperature variations which impact helium purge gas flow as well as Q2 composition concentration time and space evolutions in the breeding regions. This affords a more accurate prediction of tritium permeation into the He coolant by accounting correct temperature and partial pressure effects and realistic diffusion paths. The analysis also shows that by introducing by-pass line to accommodate ITER pulsed operations in the TES loop allows tritium extraction design being more cost effective.}, +@article{maroudas_helium_2016, + title = {Helium segregation on surfaces of plasma-exposed tungsten}, + volume = {28}, + issn = {0953-8984}, + url = {https://doi.org/10.1088%2F0953-8984%2F28%2F6%2F064004}, + doi = {10.1088/0953-8984/28/6/064004}, + abstract = {We report a hierarchical multi-scale modeling study of implanted helium segregation on surfaces of tungsten, considered as a plasma facing component in nuclear fusion reactors. We employ a hierarchy of atomic-scale simulations based on a reliable interatomic interaction potential, including molecular-statics simulations to understand the origin of helium surface segregation, targeted molecular-dynamics (MD) simulations of near-surface cluster reactions, and large-scale MD simulations of implanted helium evolution in plasma-exposed tungsten. We find that small, mobile He n (1 ⩽ n ⩽ 7) clusters in the near-surface region are attracted to the surface due to an elastic interaction force that provides the thermodynamic driving force for surface segregation. This elastic interaction force induces drift fluxes of these mobile He n clusters, which increase substantially as the migrating clusters approach the surface, facilitating helium segregation on the surface. Moreover, the clusters’ drift toward the surface enables cluster reactions, most importantly trap mutation, in the near-surface region at rates much higher than in the bulk material. These near-surface cluster dynamics have significant effects on the surface morphology, near-surface defect structures, and the amount of helium retained in the material upon plasma exposure. We integrate the findings of such atomic-scale simulations into a properly parameterized and validated spatially dependent, continuum-scale reaction-diffusion cluster dynamics model, capable of predicting implanted helium evolution, surface segregation, and its near-surface effects in tungsten. This cluster-dynamics model sets the stage for development of fully atomistically informed coarse-grained models for computationally efficient simulation predictions of helium surface segregation, as well as helium retention and surface morphological evolution, toward optimal design of plasma facing components.}, language = {en}, - urldate = {2021-01-12}, - journal = {Fusion Engineering and Design}, - author = {Ying, Alice and Zhang, Hongjie and Merrill, Brad J. and Ahn, Mu-Young}, - month = nov, + number = {6}, + urldate = {2020-01-14}, + journal = {Journal of Physics: Condensed Matter}, + author = {Maroudas, Dimitrios and Blondel, Sophie and Hu, Lin and Hammond, Karl D. and Wirth, Brian D.}, + month = jan, year = {2016}, - keywords = {Numerical modeling, Ceramic breeder blankets, Purge gas flow, Tritium transport and permeation}, - pages = {1511--1516}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9UZ9UTY9\\Ying et al. - 2016 - Advancement in tritium transport simulations for s.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X4BLSXTE\\S0920379615303719.html:text/html}, + pages = {064004}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SFKLHLKE\\Maroudas et al. - 2016 - Helium segregation on surfaces of plasma-exposed t.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MAUQ4VWI\\pdf.html:text/html}, } -@article{farabolini_tritium_2006, - series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, - title = {Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor}, - volume = {81}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S092037960500582X}, - doi = {10.1016/j.fusengdes.2005.07.018}, - abstract = {In this paper, we present computations linking the tritium release rate to the characteristics of lithium–lead and helium cooling circuits. Impacting component performances are evaluated such as tritium permeation towards the He coolant in the blanket modules, lithium–lead circulation rate, tritium extraction unit efficiency, tritium permeation in steam generator, helium coolant leak rate, helium purification unit maximum flow rate and efficiency. Safety considerations are also taken into account. A finite element model (FEM) for tritium permeation was developed considering various phenomena such as tritium transport by convection and diffusion in lithium–lead, MHD effects on liquid metal flows, tritium permeation in structures with temperature gradients. Other sub-system performances, like He leak rate and efficiency of tritium extraction systems, are discussed via an engineering approach. The results show that a reasonable compromise among the various requirements can be found, leading to technologically achievable requirements for tritium permeation barriers, tritium extraction systems both from Pb–17Li and He, and leak rates from the He cooling system.}, +@article{alnaes_fenics_2015, + title = {The {FEniCS} {Project} {Version} 1.5}, + volume = {3}, + copyright = {Copyright (c) 2015 Archive of Numerical Software}, + issn = {2197-8263}, + url = {https://journals.ub.uni-heidelberg.de/index.php/ans/article/view/20553}, + doi = {10.11588/ans.2015.100.20553}, + abstract = {The FEniCS Project is a collaborative project for the development of innovative concepts and tools for automated scientific computing, with a particular focus on the solution of differential equations by finite element methods. The FEniCS Projects software consists of a collection of interoperable software components, including DOLFIN, FFC, FIAT, Instant, UFC, UFL, and mshr. This note describes the new features and changes introduced in the release of FEniCS version 1.5.}, language = {en}, - number = {1}, - urldate = {2021-01-12}, - journal = {Fusion Engineering and Design}, - author = {Farabolini, W. and Ciampichetti, A. and Dabbene, F. and Fütterer, M. A. and Giancarli, L. and Laffont, G. and Puma, A. Li and Raboin, S. and Poitevin, Y. and Ricapito, I. and Sardain, P.}, - month = feb, - year = {2006}, - keywords = {Tritium, Fusion blanket, Lithium–lead, Permeation}, - pages = {753--762}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7N36TTF5\\Farabolini et al. - 2006 - Tritium control modelling for a helium cooled lith.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6HP5LMS7\\S092037960500582X.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TQ3ILGZX\\S092037960500582X.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RFVUBMUT\\Farabolini et al. - 2006 - Tritium control modelling for a helium cooled lith.pdf:application/pdf}, + number = {100}, + urldate = {2019-10-07}, + journal = {Archive of Numerical Software}, + author = {Alnæs, Martin and Blechta, Jan and Hake, Johan and Johansson, August and Kehlet, Benjamin and Logg, Anders and Richardson, Chris and Ring, Johannes and Rognes, Marie E. and Wells, Garth N.}, + month = dec, + year = {2015}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\DFTKYF4Q\\Alnæs et al. - 2015 - The FEniCS Project Version 1.5.pdf:application/pdf;Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ZQF3NK8H\\Alnæs et al. - 2015 - The FEniCS Project Version 1.5.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\LU5SQ6FV\\20553.html:text/html}, } @article{bufferand_three-dimensional_2019, @@ -5231,3029 +5188,3275 @@ @article{bufferand_three-dimensional_2019 year = {2019}, keywords = {Edge plasma, Fluid modelling, Impurity transport, Turbulence}, pages = {82--86}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G4MYWVC2\\Bufferand et al. - 2019 - Three-dimensional modelling of edge multi-componen.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2SDGPXZN\\S2352179118302035.html:text/html}, -} - -@article{shimwell_paramak_2021, - title = {The {Paramak}: automated parametric geometry construction for fusion reactor designs.}, - volume = {10}, - copyright = {All rights reserved}, - issn = {2046-1402}, - shorttitle = {The {Paramak}}, - url = {https://f1000research.com/articles/10-27/v1}, - doi = {10.12688/f1000research.28224.1}, - abstract = {During the conceptual design process of fusion reactors it is useful to rapidly prototype different design concepts and assess their suitability against a range of high level requirements. Rapid prototyping allows the 'fail early' mantra of other fields to be applied to engineering design. - Furthermore, the rapid generation of low fidelity analysis allows fast exploration of design space, which enables better decisions to be made during concept selection and the detailed design phase. The Paramak is an open-source tool that aims to provide automated parameter driven 3D CAD models for fusion reactor components and magnetic fusion reactors. The geometry produced is compatible with several analysis workflows and this allows iterative automated model building and analysis to help steer the design concept optimisation process. The Paramak uses CadQuery 2 to create the 3D CAD model. The Paramak framework is used to create a few example reactor configurations including: a spherical reactor, a regular large radius tokamak and a compact submersion tank reactor. Input parameters for the various reactors that the Paramak can generate generally fall into three categories: continuous ranges such as blanket thickness, integer ranges such as number of toroidal field coils and categorical parameters such as type of divertor. The Paramak facilitates parameter studies where users can investigate the impact of input design parameters on the reactor performance. The use of modern software practices allows the geometry to be continuously tested in analysis workflows to ensure it is fit for purpose. The generation of output metrics from input parameters lends itself to the use of data science and machine learning approaches in order to steer the design. The Paramak provides rapid construction of analysis ready CAD in a manner that allows the designer to save time when exploring the design space for design studies and facilitate automated generative design.}, - language = {en}, - urldate = {2021-01-18}, - journal = {F1000Research}, - author = {Shimwell, Jonathan and Billingsley, John and Delaporte-Mathurin, Rémi and Morbey, Declan and Bluteau, Matthew and Shriwise, Patrick and Davis, Andrew}, - month = jan, - year = {2021}, - pages = {27}, - file = {Shimwell et al. - 2021 - The Paramak automated parametric geometry constru.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U5RQK6W4\\Shimwell et al. - 2021 - The Paramak automated parametric geometry constru.pdf:application/pdf}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\G4MYWVC2\\Bufferand et al. - 2019 - Three-dimensional modelling of edge multi-componen.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2SDGPXZN\\S2352179118302035.html:text/html}, } -@article{boisse_modeling_2014, - title = {Modeling of the self trapping of helium and the trap mutation in tungsten using {DFT} and empirical potentials based on {DFT}}, - volume = {29}, - issn = {0884-2914, 2044-5326}, - url = {https://www.cambridge.org/core/journals/journal-of-materials-research/article/abs/modeling-of-the-self-trapping-of-helium-and-the-trap-mutation-in-tungsten-using-dft-and-empirical-potentials-based-on-dft/8E4976DED47CF5267DAEBEA9F8D84F9F}, - doi = {10.1557/jmr.2014.258}, - abstract = {, - Density functional theory calculations and molecular dynamics with a recently developed potential for W–He were used to evaluate the thermal stability of helium-vacancy clusters (nHe.mv) as well as pure interstitial helium clusters in tungsten. The stability of such objects results from a competitive process between thermal emission of vacancies, self interstitial atoms (SIAs), and helium, depending on the helium-to-vacancy ratio in mixed clusters or helium number in pure interstitial helium clusters. We investigated in particular the ground state configurations as well as the activation barriers of self trapping and trap mutation, i.e., the emission of one SIA along with the creation of one vacancy from a vacancy-helium or pure helium object.}, +@article{ying_advancement_2016, + series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, + title = {Advancement in tritium transport simulations for solid breeding blanket system}, + volume = {109-111}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379615303719}, + doi = {10.1016/j.fusengdes.2015.11.040}, + abstract = {In this paper, advancement on tritium transport simulations was demonstrated for a solid breeder blanket HCCR TBS, where multi-physics and detailed engineering descriptions are considered using a commercial simulation code. The physics involved includes compressible purge gas fluid flow, heat transfer, chemical reaction, isotope swamping effect, and tritium isotopes mass transport. The strategy adopted here is to develop numerical procedures and techniques that allow critical details of material, geometric and operational heterogeneity in a most complete engineering description of the TBS being incorporated into the simulation. Our application focuses on the transient assessment in view of ITER being pulsed operations. An immediate advantage is a more realistic predictive and design analysis tool accounting pulsed operations induced temperature variations which impact helium purge gas flow as well as Q2 composition concentration time and space evolutions in the breeding regions. This affords a more accurate prediction of tritium permeation into the He coolant by accounting correct temperature and partial pressure effects and realistic diffusion paths. The analysis also shows that by introducing by-pass line to accommodate ITER pulsed operations in the TES loop allows tritium extraction design being more cost effective.}, language = {en}, - number = {20}, - urldate = {2021-01-22}, - journal = {Journal of Materials Research}, - author = {Boisse, J. and Backer, A. De and Domain, C. and Becquart, C. S.}, - month = oct, - year = {2014}, - note = {Publisher: Cambridge University Press}, - keywords = {helium, self trapping, simulation, trap mutation, tungsten, custom}, - pages = {2374--2386}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FJKQWK2W\\8E4976DED47CF5267DAEBEA9F8D84F9F.html:text/html;Boisse et al. - 2014 - Modeling of the self trapping of helium and the tr.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5WDXA55D\\Boisse et al. - 2014 - Modeling of the self trapping of helium and the tr.pdf:application/pdf}, + urldate = {2021-01-12}, + journal = {Fusion Engineering and Design}, + author = {Ying, Alice and Zhang, Hongjie and Merrill, Brad J. and Ahn, Mu-Young}, + month = nov, + year = {2016}, + keywords = {Ceramic breeder blankets, Numerical modeling, Purge gas flow, Tritium transport and permeation}, + pages = {1511--1516}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\9UZ9UTY9\\Ying et al. - 2016 - Advancement in tritium transport simulations for s.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\X4BLSXTE\\S0920379615303719.html:text/html}, } -@article{vizvary_european_2020, - title = {European {DEMO} first wall shaping and limiters design and analysis status}, - volume = {158}, - issn = {0920-3796}, - url = {http://www.sciencedirect.com/science/article/pii/S0920379620302246}, - doi = {10.1016/j.fusengdes.2020.111676}, - abstract = {The anticipated heat flux limit of the European DEMO first wall is ∼1−2 MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected. This involves dedicated discrete limiters in certain regions of the machine that would take the brunt of the heat load as well as adequate shaping of the first wall. The current concept envisages limiters at a few (3–4) equatorial ports to cope with the ramp-up of the plasma; upper limiters (in ∼8 upper ports) are considered for upward vertical displacement events. Two design options have been considered for these limiters: a modular design where the limiter plasma facing components are attached to individual plates that are assembled together so that transient electromagnetic loads can be reduced, and in case of damage the plates can be replaced/repaired individually; and a divertor-like design where the plasma facing components are attached to a single Eurofer cassette. Other limiters considered include inner wall limiters in case of plasma contraction and lower limiters may be needed for downward vertical displacement events. The thermal hydraulic finite element analysis results show that the integrity of the cooling pipes can be maintained during the anticipated transient events. The limiters are considered to be sacrificial and designed to be replaceable independently from the breeding blanket system. The design has to allow that installation, removal or replacement of the limiters can be performed remotely. Strategy to tackle outstanding issues and required R\&D is also discussed.}, +@article{hollingsworth_comparative_2019, + title = {Comparative study of deuterium retention in irradiated {Eurofer} and {Fe}–{Cr} from a new ion implantation materials facility}, + volume = {60}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Fab546e}, + doi = {10.1088/1741-4326/ab546e}, + abstract = {A new facility to study the interaction of hydrogen isotopes with nuclear fusion-relevant first wall materials, and their retention and release, has been produced. The new facility allows for implanting a range of gases into samples, including tritium. An accurate study of isotope effects, such as the isotopic exchange in damaged microstructure, has previously been difficult due to a background signal of light hydrogen. This new capability will allow virtually background free measurements using tritium and deuterium. The design and build of this facility are described and commissioning results are presented. Within the UKAEA-led tritium retention in controlled and evolving microstructure (TRiCEM) project, this facility is used for the comparative study of deuterium retention in self-ion irradiated Eurofer steel and Fe–Cr alloy. Self-ion bombardment with energies of 0.5 MeV is used to mimic the defects created by neutrons in fusion power plants and the created traps are then filled with deuterium in the new facility. Implanted samples are analysed using thermal desorption spectrometry (TDS), secondary ion mass spectrometry (SIMS), and transmission electron microscopy. Results on the total deuterium content as a function of time, TDS spectra and SIMS analysis are presented. A comparison of the results for Eurofer and Fe–Cr revealed several differences. While some of them may be due to experimental details like different time delays between exposure and analysis, others, such as deuterium retention as function of dose, might be genuine and require further studies.}, language = {en}, - urldate = {2021-01-25}, - journal = {Fusion Engineering and Design}, - author = {Vizvary, Z. and Arter, W. and Bachmann, C. and Barrett, T. R. and Chuilon, B. and Cooper, P. and Flynn, E. and Firdaouss, M. and Franke, T. and Gerardin, J. and Gowland, R. and Kovari, M. and Maviglia, F. and Richiusa, M. L. and Adame, E. V. Rosa and Vorpahl, C. and Wilde, A. and Xue, Y.}, - month = sep, - year = {2020}, - keywords = {DEMO, First Wall shaping, Limiter, PFC, Thermo-hydraulic analysis}, - pages = {111676}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YLGQCQT5\\Vizvary et al. - 2020 - European DEMO first wall shaping and limiters desi.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2PYYULC8\\S0920379620302246.html:text/html}, + number = {1}, + urldate = {2020-04-10}, + journal = {Nuclear Fusion}, + author = {Hollingsworth, A. and Lavrentiev, M. Yu and Watkins, R. and Davies, A. C. and Davies, S. and Smith, R. and Mason, D. R. and Baron-Wiechec, A. and Kollo, Z. and Hess, J. and Jepu, I. and Likonen, J. and Heinola, K. and Mizohata, K. and Meslin, E. and Barthe, M.-F. and Widdowson, A. and Grech, I. S. and Abraham, K. and Pender, E. and McShee, A. and Martynova, Y. and Freisinger, M. and Backer, A. De}, + month = nov, + year = {2019}, + note = {Publisher: IOP Publishing}, + pages = {016024}, + file = {Hollingsworth et al. - 2019 - Comparative study of deuterium retention in irradi.pdf:D\:\\Logiciels\\data_zotero\\storage\\YEXXT4SV\\Hollingsworth et al. - 2019 - Comparative study of deuterium retention in irradi.pdf:application/pdf}, } -@article{wei_shape_2010, - title = {The shape of bubbles in {He}-implanted {Cu} and {Au}}, - volume = {63}, - issn = {1359-6462}, - url = {http://www.sciencedirect.com/science/article/pii/S135964621000299X}, - doi = {10.1016/j.scriptamat.2010.04.043}, - abstract = {Bubble evolution under thermal annealing has been studied in He-implanted Cu and Au by in situ transmission electron microscopy. We show that, under the minimum energy requirement of system, the bubble developed into an octahedron (or truncated octahedron) shape consisting of \{111\} planes in the manner predicted by the Wulff construction. The non-spherical shape of the bubbles and the existence of sessile dislocations along the edges of octahedron provide a barrier to Ostwald ripening and migration of bubbles, leading to low bubble mobility under thermal annealing.}, +@article{ogorodnikova_recombination_2019, + title = {Recombination coefficient of hydrogen on tungsten surface}, + volume = {522}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311519300030}, + doi = {10.1016/j.jnucmat.2019.05.017}, + abstract = {The recombination coefficient is an important parameter for modelling hydrogen-metal interaction. It is responsible for hydrogen desorption from the surface of the metal and, therefore, significantly affects the hydrogen penetration into the metal, accumulation in and permeation through the metal. In the present work, the recombination coefficient of hydrogen (H) on tungsten (W) surface is examined. It is shown that the recombination coefficient of H on a clean W surface is extremely high which indicates the rapid desorption of the hydrogen molecule from the surface. Simulation using a high recombination coefficient well describes a wide range of experimental data of gas and ions interaction of hydrogen isotopes with tungsten. Proof of incorrectness of the Anderl's recombination coefficient is presented by comparing it with both theory and experiment.}, language = {en}, - number = {4}, - urldate = {2021-01-30}, - journal = {Scripta Materialia}, - author = {Wei, Qiangmin and Li, Nan and Sun, Kai and Wang, L. M.}, + urldate = {2020-04-01}, + journal = {Journal of Nuclear Materials}, + author = {Ogorodnikova, O. V.}, month = aug, - year = {2010}, - keywords = {Copper, Annealing, Implantation, Transmission electron microscopy (TEM)}, - pages = {430--433}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NWTPCXSV\\S135964621000299X.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\C8BDLF7T\\Wei et al. - 2010 - The shape of bubbles in He-implanted Cu and Au.pdf:application/pdf}, + year = {2019}, + pages = {74--79}, + file = {Ogorodnikova - 2019 - Recombination coefficient of hydrogen on tungsten .pdf:D\:\\Logiciels\\data_zotero\\storage\\X5VH4RC2\\Ogorodnikova - 2019 - Recombination coefficient of hydrogen on tungsten .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\RNBPEF6F\\S0022311519300030.html:text/html}, } -@article{pick_model_1985, - title = {A model for atomic hydrogen-metal interactions — application to recycling, recombination and permeation}, - volume = {131}, - issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/0022311585904593}, - doi = {10.1016/0022-3115(85)90459-3}, - abstract = {A model for the interaction of hydrogen with metals is discussed which includes the surface concentration and the surface potential and is based on the observation that molecular hydrogen is dissociated before it is chemisorbed at a metal surface. It is shown that an activation barrier for dissociation of molecular hydrogen at the metal surface leads to an enhanced solubility and increased permeation rate of hydrogen in a metal exposed to atomic hydrogen as compared to molecular hydrogen. The sticking probability of molecular hydrogen on clean transition metals has been measured in the past and shown to be of the order of unity. As no activation barrier is present no difference is expected between atomic and molecular hydrogen. Whenever large differences have been observed in the past they must be attributed to an impurity contamination of the metal surface. Substantial reductions of the sticking probability due to dissociation barriers have been found for metals contaminated with less than one monolayer of electronegative impurities. We compare our model with earlier descriptions of hydrogen metal interactions. A theoretical expression is derived for the “recombination rate constant”. Furthermore we discuss implications of our model on hydrogen permeation (“super permeation”) as well as hydrogen pumping and pumping panels in tokamaks.}, +@article{turnbull_modelling_1997, + title = {Modelling of thermal desorption of hydrogen from metals}, + volume = {238}, + issn = {0921-5093}, + url = {http://www.sciencedirect.com/science/article/pii/S0921509397004267}, + doi = {10.1016/S0921-5093(97)00426-7}, + abstract = {The thermal desorption technique can be used in principle to determine the trapping characteristics of different microstructural trap sites in metals provided there are adequate models to fit to the experimental data. A brief review of models of thermal desorption is presented which indicates that there are limitations in the assumptions made or in the scope of existing models. A more rigorous mathematical model has now been developed which accounts for diffusion, detrapping, and retrapping at one or more type of trap site and which allows for varying trap occupancy. The effect of material and experimental variables on the thermal desorption spectrum has been evaluated and the validity of simple models of desorption assessed. The simpler analytical models, such as the detrapping model of Lee and Lee, in which diffusion is neglected relative to detrapping, do not inspire confidence and are applicable only under very limiting circumstances; for example, in low alloy steels at very low hydrogen contents. It is recommended that thermal desorption measurements be made at progressively decreasing values of initial hydrogen content until the simple analysis yields a consistent value for the trapping parameters. This experimental approach is applicable also to models of thermal desorption which account for diffusion using an effective diffusivity, since trap occupancy is neglected in these. The more rigorous model described herein can be used to determine the binding energy of the traps directly which, together with the density of trap sites, is the most important parameter with respect to hydrogen assisted cracking. The height of the energy barrier to trapping, at constant value of the binding energy, is shown to have only a modest effect on the thermal desorption spectrum compared with the impact of binding energy and of density of trap sites.}, language = {en}, number = {2}, - urldate = {2021-01-26}, - journal = {Journal of Nuclear Materials}, - author = {Pick, M. A. and Sonnenberg, K.}, - month = apr, - year = {1985}, - pages = {208--220}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FTWVWFIG\\0022311585904593.html:text/html}, + urldate = {2020-01-27}, + journal = {Materials Science and Engineering: A}, + author = {Turnbull, A and Hutchings, R. B and Ferriss, D. H}, + month = nov, + year = {1997}, + keywords = {Hydrogen, Metals, Thermal desorption, Modeling}, + pages = {317--328}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\LL4BE5YA\\Turnbull et al. - 1997 - Modelling of thermal desorption of hydrogen from m.pdf:application/pdf;ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\6KKKICHN\\Turnbull et al. - 1997 - Modelling of thermal desorption of hydrogen from m.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7FVXEMJK\\S0921509397004267.html:text/html;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\EC588WWB\\S0921509397004267.html:text/html}, +} + +@article{denis_dynamic_2019, + title = {Dynamic modelling of local fuel inventory and desorption in the whole tokamak vacuum vessel for auto-consistent plasma-wall interaction simulations}, + volume = {19}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S235217911830262X}, + doi = {10.1016/j.nme.2019.03.019}, + abstract = {An extension of the SolEdge2D-EIRENE code package, named D-WEE, has been developed to add the dynamics of thermal desorption of hydrogen isotopes from the surface of plasma facing materials. To achieve this purpose, D-WEE models hydrogen isotopes implantation, transport and retention in those materials. Before launching auto-consistent simulation (with feedback of D-WEE on SolEdge2D-EIRENE), D-WEE has to be initialised to ensure a realistic wall behaviour in terms of dynamics (pumping or fuelling areas) and fuel content. A methodology based on modelling is introduced to perform such initialisation. A synthetic plasma pulse is built from consecutive SolEdge2D-EIRENE simulations. This synthetic pulse is used as a plasma background for the D-WEE module. A sequence of plasma pulses is simulated with D-WEE to model a tokamak operation. This simulation enables to extract at a desired time during a pulse the local fuel inventory and the local desorption flux density which could be used as initial condition for coupled plasma-wall simulations. To assess the relevance of the dynamic retention behaviour obtained in the simulation, a confrontation to post-pulse experimental pressure measurement is performed. Such confrontation reveals a qualitative agreement between the temporal pressure drop obtained in the simulation and the one observed experimentally. The simulated dynamic retention during the consecutive pulses is also studied.}, + language = {en}, + urldate = {2020-03-13}, + journal = {Nuclear Materials and Energy}, + author = {Denis, J. and Bucalossi, J. and Ciraolo, G. and Hodille, E. A. and Pégourié, B. and Bufferand, H. and Grisolia, C. and Loarer, T. and Marandet, Y. and Serre, E.}, + month = may, + year = {2019}, + keywords = {Dynamic retention, Dynamics of hydrogen isotopes thermal desorption, Edge plasma physics, Plasma-wall interaction simulation, Recycling}, + pages = {550--557}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YKZINC8E\\Denis et al. - 2019 - Dynamic modelling of local fuel inventory and deso.pdf:application/pdf}, } -@article{moro_neutronic_2018, - series = {Special {Issue}: {Proceedings} of the 13th {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-13)}, - title = {Neutronic analyses in support of the {WCLL} {DEMO} design development}, - volume = {136}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379618304071}, - doi = {10.1016/j.fusengdes.2018.04.113}, - abstract = {In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design. Neutronic analyses play a fundamental role in the development of the WCLL blanket, providing guidelines for its design based on the evaluation of the nuclear performances. A detailed three-dimensional MCNP model of the latest WCLL layout has been generated and integrated in a DEMO MCNP generic model suitably designed for neutronic analyses. Three-dimensional neutron and gamma transport simulations have been performed using the MCNP5v1.6 Monte Carlo code and JEFF 3.2 nuclear data libraries, in order to assess the WCLL-DEMO tritium self-sufficiency and the shielding capabilities of the breeding blanket/manifold system to protect the vacuum vessel and toroidal field coils. Furthermore, radial profiles of the neutron flux, nuclear heating, neutron damage and he-production have been assessed in the inboard and outboard equatorial planes. The outcome of the present study highlights the potential and suitability of the WCLL breeding blanket for the application to DEMO, both in terms of tritium production and shielding performances.}, - language = {en}, - urldate = {2021-02-22}, - journal = {Fusion Engineering and Design}, - author = {Moro, Fabio and Del Nevo, Alessandro and Flammini, Davide and Martelli, Emanuela and Mozzillo, Rocco and Noce, Simone and Villari, Rosaria}, - month = nov, - year = {2018}, - keywords = {DEMO, WCLL, Nuclear, MCNP, Neutronics, Shielding, TBR}, - pages = {1260--1264}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5CF4QJWJ\\S0920379618304071.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MGVHC34W\\Moro et al. - 2018 - Neutronic analyses in support of the WCLL DEMO des.pdf:application/pdf}, +@misc{noauthor_solute_nodate, + title = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment - {IOPscience}}, + url = {https://iopscience.iop.org/article/10.1088/1402-4896/ab4b42}, + urldate = {2020-03-30}, + file = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment - IOPscience:D\:\\Logiciels\\data_zotero\\storage\\TZ22YHLS\\ab4b42.html:text/html}, } -@article{edemetti_impact_2020, - title = {On the impact of the heat transfer modelling approach on the prediction of {EU}-{DEMO} {WCLL} breeding blanket thermal performances}, - volume = {161}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379620305998}, - doi = {10.1016/j.fusengdes.2020.112051}, - abstract = {The Water-Cooled Lithium-Lead Breeding Blanket is a key component of a fusion power plant, in charge of ensure Tritium production, shield Vacuum Vessel and magnets and remove the heat power deposited by radiation and particles arising from plasma. The last function is fulfilled by First Wall and Breeding Zone independent cooling systems. Several layouts of BZ coolant system have been investigated in the last years to identify a configuration that might guarantee EUROFER temperature below the limit (550 °C) and good thermal-hydraulic performances (i.e. water outlet temperature of 328 °C). A research activity is conducted to study and compare different modelling approaches to simulate the heat transfer within the BZ liquid metal, assessing their impact on the numerical prediction of the WCLL blanket thermal performances. An approach will rely on the simulation of convective and diffusive heat transfer processes taking place within the liquid metal by means of a CFD tool based on the Finite Volume Method. Conversely, the other approach will roughly assume a pure diffusive heat transfer mechanism within the breeder, due to the very low velocities envisaged for its flow field. In this case the heat transfer performances will be preferably assessed by means of a commercial code based on the Finite Element Method. The analyses have been carried out with reference to the so called “WCLL BB 2018 V0.6″ equatorial cell. Advantages and issues from the thermal-hydraulic point of view are identified, the impact of the imposed boundary conditions and heat transfer properties, with the implemented correlations, on the respective results is critically discussed.}, +@misc{noauthor_shape_nodate, + title = {The shape of bubbles in {He}-implanted {Cu} and {Au} - {ScienceDirect}}, + url = {https://www.sciencedirect.com/science/article/pii/S135964621000299X}, + urldate = {2020-03-16}, + keywords = {Bubbles}, + file = {The shape of bubbles in He-implanted Cu and Au - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\YKBGS6KT\\S135964621000299X.html:text/html}, +} + +@article{benannoune_multidimensional_2020, + title = {Multidimensional finite-element simulations of the diffusion and trapping of hydrogen in plasma-facing components including thermal expansion}, + volume = {T171}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F1402-4896%2Fab4335}, + doi = {10.1088/1402-4896/ab4335}, + abstract = {This study is focused on tritium retention and permeation through a 316L stainless steel diagnostic first wall during plasma operations in ITER. A set of data for migration properties is proposed by adjusting the values to fit a simulation using experimental results. A reactive–diffusion model coupled with a mechanical field, solved on 3DS Abaqus finite-element software, is applied to estimate tritium migration. Two-dimensional simulations are compared with one-dimensional simulations and the role of thermal expansion on plastic deformation and trap creation is discussed.}, language = {en}, - urldate = {2021-02-22}, - journal = {Fusion Engineering and Design}, - author = {Edemetti, Francesco and Martelli, Emanuela and Del Nevo, Alessandro and Giannetti, Fabio and Arena, Pietro and Forte, Ruggero and Di Maio, Pietro Alessandro and Caruso, Gianfranco}, - month = dec, + urldate = {2020-03-13}, + journal = {Physica Scripta}, + author = {Benannoune, Sofiane and Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique and Temmerman, Greg De}, + month = jan, year = {2020}, - keywords = {Breeding blanket, WCLL, Blanket engineering, CFD, FEM}, - pages = {112051}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\36ADAL4Y\\S0920379620305998.html:text/html}, + pages = {014011}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\95HNAEV2\\Benannoune et al. - 2020 - Multidimensional finite-element simulations of the.pdf:application/pdf}, } -@article{liao_first-principles_2020, - title = {First-principles study of helium behavior in nickel with noble gas incorporation}, - volume = {127}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.5145016}, - doi = {10.1063/1.5145016}, - number = {17}, - urldate = {2021-02-19}, - journal = {Journal of Applied Physics}, - author = {Liao, Liang-Xiang and Zhang, Xun and Ren, Cui-Lan and Zhang, Zheng-De and Huang, He-Fei and Ma, Guo-Hong and Huai, Ping}, - month = may, +@article{khan_helium_2020, + title = {Helium irradiation effects on the surface modification and recrystallization of tungsten}, + volume = {T171}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F1402-4896%2Fab52c6}, + doi = {10.1088/1402-4896/ab52c6}, + abstract = {Helium (He) irradiation has previously been observed to alter surface modifications and the recrystallization properties of tungsten (W). In this study, He irradiations in the NAGDIS-II linear plasma device, at temperatures below recrystallization and low energies (50 eV) followed by annealing at 1470 K were carried out. Additionally, high energy (28 keV) hydrogen (H) with an admixture of 6 at\% He irradiations in the neutral beam facility GLADIS were performed at temperatures above recrystallization (1770 K). These are compared to pure H irradiations under the same conditions. In the low temperature cases, following irradiation, an undulating microstructure is observed on the surface of the samples after irradiation. After annealing at 1470 K, it is observed that the inhibition effect of He irradiation is more pronounced following lower temperature exposures. The effect of He irradiation on inhibition of recrystallization with grain growth is also observed to saturate at the highest fluences. In the high temperature, high energy case, He irradiation and recrystallization happens simultaneously. Following the irradiation a coral like microstructure is observed on the surface of the sample. The introduction of He is not seen to have a significant effect on the recrystallization process of W when the irradiation is carried out at temperatures above recrystallization.}, + language = {en}, + urldate = {2020-03-13}, + journal = {Physica Scripta}, + author = {Khan, A. and Temmerman, G. De and Kajita, S. and Greuner, H. and Balden, M. and Hunger, K. and Ohno, N. and Hwangbo, D. and Tomita, Y. and Tokitani, M. and Nagata, D. and Yajima, M.}, + month = jan, year = {2020}, - note = {Publisher: American Institute of Physics}, - pages = {175903}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PHLZP55J\\1.html:text/html}, + pages = {014050}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\J2Z897XD\\Khan et al. - 2020 - Helium irradiation effects on the surface modifica.pdf:application/pdf}, } -@article{meszaros_definition_2015, - series = {Proceedings of the 28th {Symposium} {On} {Fusion} {Technology} ({SOFT}-28)}, - title = {Definition of the basic {DEMO} tokamak geometry based on systems code studies}, - volume = {98-99}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379615301265}, - doi = {10.1016/j.fusengdes.2015.06.097}, - abstract = {This paper describes the methodology that has been developed and applied to derive the principal geometry of the main DEMO tokamak systems, in particular the radial and vertical cross section based on the systems code output parameters, while exact parameters are described elsewhere [1]. This procedure reviews the analysis of the radial and vertical build provided by the system code to verify critical integration interfaces, e.g. missing or too large gaps and/or insufficient thickness of components, and updates these dimensions based on results of more detailed analyses (e.g. neutronics, plasma scenario modelling, etc.) that were carried out outside of the system code in the past years. As well as providing a 3D configuration model of the DEMO tokamak for integrated engineering analysis, the results can also be used to refine the systems code model. This method, subject to continuous refinement, controls the derivation of the main machine parameters and ensures their coherence vis-à-vis a number of agreed controlled physics and engineering assumptions.}, +@article{sharafat_description_2009, + series = {Fusion {Reactor} {Materials}}, + title = {A description of bubble growth and gas release of helium implanted tungsten}, + volume = {386-388}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311508010155}, + doi = {10.1016/j.jnucmat.2008.12.318}, + abstract = {Bubble growth and gas release during annealing of helium implanted tungsten is described using a Kinetic Monte Carlo approach. Implantation of tungsten with low energy He ions results in the unusual formation of large numbers of oversized surface pores, which eventually lead to drastic changes of the tungsten surface morphology. Traditional rate-theory models are not suitable to simulate surface pore formation. Results of the KMC simulations illustrate the rapid formation of very large helium bubbles and surface pores. The simulation results agree well with observed results of low energy He implanted tungsten experiments, and thus provide an explanation for the observed surface morphology changes caused by low energy He implantation of tungsten.}, language = {en}, - urldate = {2021-02-16}, - journal = {Fusion Engineering and Design}, - author = {Meszaros, Botond and Bachmann, Christian and Kemp, Richard and Federici, Gianfranco}, - month = oct, - year = {2015}, - keywords = {DEMO, Nuclear fusion, Systems code, Configuration, Geometry, PROCESS}, - pages = {1556--1560}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DS32BLBM\\Meszaros et al. - 2015 - Definition of the basic DEMO tokamak geometry base.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7A64DVGQ\\S0920379615301265.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Q2ZUDY8S\\Meszaros et al. - 2015 - Definition of the basic DEMO tokamak geometry base.pdf:application/pdf}, + urldate = {2020-03-11}, + journal = {Journal of Nuclear Materials}, + author = {Sharafat, S. and Takahashi, A. and Hu, Q. and Ghoniem, N. M.}, + month = apr, + year = {2009}, + pages = {900--903}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\UWY9JXNY\\Sharafat et al. - 2009 - A description of bubble growth and gas release of .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\E8DC44B6\\S0022311508010155.html:text/html}, } -@article{federici_european_2017, - title = {European {DEMO} design strategy and consequences for materials}, - volume = {57}, +@article{reinhart_diffusion_2019, + title = {Diffusion model of the impact of helium and argon impurities on deuterium retention in tungsten}, + volume = {59}, issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/57/9/092002}, - doi = {10.1088/1741-4326/57/9/092002}, - abstract = {Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather ‘proxies’ of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed ‘low extrapolation’ system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device.}, + url = {https://doi.org/10.1088%2F1741-4326%2Faafe8d}, + doi = {10.1088/1741-4326/aafe8d}, + abstract = {The influence of helium and argon impurities on the deuterium retention in tungsten is investigated by a numerical diffusion model, which treats diffusing depth profiles for deuterium and helium or argon in tungsten, taking into account the suggested effects of helium or argon. With helium, a helium nanobubble layer builds up at the surface of the sample, with depths higher than the penetration depth of the incident helium and deuterium ions. The nanobubbles form a porous network, which allows the release of trapped deuterium by surface recombination and diffusion through the pores to the surface. For argon, only a shallow layer of argon-induced defects exists, which also act as trapping sites for deuterium. A number of experiments with tungsten samples were conducted at the linear plasma device PSI-2 in support of the model. Helium and argon were admixed to deuterium plasma in ratios of up to 8\% for otherwise similar exposure conditions. In addition, a variation of ion fluences was performed for investigation of the onset and evolution of the effects of impurities. The model shows that the influence on the deuterium retention both for helium nanobubbles as well as for argon-induced defects depends strongly on the ratio between the thickness of the helium- or argon-affected layer and the penetration depth of deuterium ions.}, language = {en}, - number = {9}, - urldate = {2021-02-16}, + number = {4}, + urldate = {2020-03-11}, journal = {Nuclear Fusion}, - author = {Federici, G. and Biel, W. and Gilbert, M. R. and Kemp, R. and Taylor, N. and Wenninger, R.}, - month = jun, - year = {2017}, - note = {Publisher: IOP Publishing}, - pages = {092002}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5S9Q5QSA\\Federici et al. - 2017 - European DEMO design strategy and consequences for.pdf:application/pdf}, + author = {Reinhart, M. and Kreter, A. and Unterberg, B. and Rasinski, M. and Linsmeier, Ch}, + month = feb, + year = {2019}, + pages = {046004}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\I7IFR6XF\\Reinhart et al. - 2019 - Diffusion model of the impact of helium and argon .pdf:application/pdf}, } -@article{hernandez_first_2018, - title = {First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors}, - volume = {137}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379618306392}, - doi = {10.1016/j.fusengdes.2018.09.014}, - abstract = {The current breeding blankets proposed in the different conceptual fusion power plants are based mainly on the use of Li4SiO4 and/or Li2TiO3 as tritium breeder and Be/Be12Ti as neutron multiplier or an eutectic Li17Pb83 for as a hybrid tritium and neutron multiplier. While these materials offer some tritium breeding capabilities, some recent studies show that the tritium self-sufficiency may not be ensured with these materials due to the strong reduction of blanket coverage after the integration of other in-vessel reactor systems (heating and current drive, limiters, large or double-null divertor systems, etc.). Also, some materials like Be raises several key feasibility concerns. The goal of this paper is to perform an update of the screening for tritium breeder and neutron multiplier materials and to assess the tritium breeding performance of the selected compounds in order to reveal new options. As for the neutron multiplier materials, a new subdivision between solid and liquid multipliers is proposed. For the selected compounds, detailed 3D heterogeneous neutronic analyses have been performed with MCNP5-1.60 assuming the architecture of the current EU DEMO Helium Cooled Pebble Bed (HCPB) as a benchmark breeding blanket. From the point of view of ceramic breeders, Li8ZrO6 has been found to outperform Li4SiO4 by more than 4\% in terms of tritium breeding, having 6\% higher melting point. From the point of view of solid neutron multipliers, Be12Cr, Be12V, Be13Zr and Be13Y show a similar performance as Be12Ti, while LaPb3, Zr5Pb4 and YPb2 offer a solution for a Be-free blanket. As for liquid multipliers, Pb in combination with a ceramic breeder shows a very promising option. Moreover, Pb compounds like Pb90Mn10 and Pb95Ba5 offer similar performance as Pb with a lower melting point (290 °C). Due to the significant advantages of molten Pb as neutron multiplier, future work will be conducted to define a design of a helium cooled Molten Lead Ceramic Breeder blanket, as simple, cost effective blanket concept.}, - language = {en}, - urldate = {2021-02-16}, - journal = {Fusion Engineering and Design}, - author = {Hernández, F. A. and Pereslavtsev, P.}, - month = dec, - year = {2018}, - keywords = {DEMO, Breeding blanket, TBR, Neutron multiplier, Tritium breeding}, - pages = {243--256}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\68Q37BXQ\\S0920379618306392.html:text/html}, +@misc{noauthor_theoretical_nodate, + title = {Theoretical {Model} of {Helium} {Bubble} {Growth} and {Density} in {Plasma}-{Facing} {Metals} {\textbar} {Scientific} {Reports}}, + url = {https://www.nature.com/articles/s41598-020-58581-8}, + urldate = {2020-03-10}, + file = {Theoretical Model of Helium Bubble Growth and Density in Plasma-Facing Metals | Scientific Reports:D\:\\Logiciels\\data_zotero\\storage\\5EPBJHSA\\s41598-020-58581-8.html:text/html}, } -@article{federici_plasma-material_2001, - title = {Plasma-material interactions in current tokamaks and their implications for next step fusion reactors}, - volume = {41}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/0029-5515/41/12/218}, - doi = {10.1088/0029-5515/41/12/218}, - abstract = {The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R\&D avenues for their resolution are presented.}, +@article{mikhlin_suppression_1979, + title = {Suppression of diffusion mobility of small gas bubbles in solids}, + volume = {56}, + issn = {00318965, 1521396X}, + url = {http://doi.wiley.com/10.1002/pssa.2210560244}, + doi = {10.1002/pssa.2210560244}, language = {en}, - number = {12}, - urldate = {2021-02-11}, - journal = {Nuclear Fusion}, - author = {Federici, G. and Skinner, C. H. and Brooks, J. N. and Coad, J. P. and Grisolia, C. and Haasz, A. A. and Hassanein, A. and Philipps, V. and Pitcher, C. S. and Roth, J. and Wampler, W. R. and Whyte, D. G.}, + number = {2}, + urldate = {2020-03-10}, + journal = {Physica Status Solidi (a)}, + author = {Mikhlin, E. Ya.}, month = dec, - year = {2001}, - note = {Publisher: IOP Publishing}, - pages = {1967--2137}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FNI9U9E5\\Federici et al. - 2001 - Plasma-material interactions in current tokamaks a.pdf:application/pdf}, + year = {1979}, + pages = {763--768}, + file = {Mikhlin - 1979 - Suppression of diffusion mobility of small gas bub.pdf:D\:\\Logiciels\\data_zotero\\storage\\S33BVJSI\\Mikhlin - 1979 - Suppression of diffusion mobility of small gas bub.pdf:application/pdf}, } -@incollection{zinkle_radiation-induced_2020, - title = {Radiation-{Induced} {Effects} on {Microstructure}}, - isbn = {978-0-08-102866-7}, - url = {https://linkinghub.elsevier.com/retrieve/pii/B9780128035818120752}, +@article{connetable_diffusion_2019, + title = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd}): {Contribution} of first and second order transition states}, + volume = {772}, + issn = {0925-8388}, + shorttitle = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd})}, + url = {http://www.sciencedirect.com/science/article/pii/S0925838818332717}, + doi = {10.1016/j.jallcom.2018.09.042}, + abstract = {We present a discussion on the influence of high-order transition states on interstitial diffusion in fcc systems using first-principles calculations. In earlier works, only first-order transition states (1TS) were used to compute the diffusivity at the atomic-scale: the direct diffusion between tetrahedral (t) and octahedral (o) sites has been proposed to describe atomic-scale diffusion mechanisms. However, we show here that if this direct diffusion makes it possible to reproduce displacements remarkably well, neglecting higher-order transition states induces an underestimation of the diffusion coefficient at high temperature. We hereinafter revisit the diffusion coefficient of interstitial species in different fcc-systems. The effect of these configurations on atom diffusion in Al, Co, Cu, Ni and Pd, whose only stable sites are the tetrahedral and octahedral positions (H and O atoms) is thus discussed here. We show that if the correction is low, taking into account higher-transition states can modify the diffusivity values at high temperature.}, language = {en}, - urldate = {2021-02-10}, - booktitle = {Comprehensive {Nuclear} {Materials}}, - publisher = {Elsevier}, - author = {Zinkle, Steven J.}, - year = {2020}, - doi = {10.1016/B978-0-12-803581-8.12075-2}, - pages = {91--129}, - file = {Zinkle - 2020 - Radiation-Induced Effects on Microstructure.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KNBSM85Z\\Zinkle - 2020 - Radiation-Induced Effects on Microstructure.pdf:application/pdf}, + urldate = {2020-02-14}, + journal = {Journal of Alloys and Compounds}, + author = {Connétable, Damien and David, Matthieu}, + month = jan, + year = {2019}, + keywords = {Diffusion, DFT, DFT calculations, Hydrogen and oxygen, Metallic systems}, + pages = {280--287}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\8KREWJZK\\Connétable et David - 2019 - Diffusion of interstitial species (H and O atoms) .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TIS3CMIZ\\S0925838818332717.html:text/html}, } -@article{dai_charpy_2005, - series = {Proceedings of the 6th {International} {Workshop} on {Spallation} {Materials} {Technology}}, - title = {Charpy impact tests on martensitic/ferritic steels after irradiation in {SINQ} target-3}, - volume = {343}, +@misc{noauthor_diffusion_nodate, + title = {Diffusion of interstitial species ({H} and {O} atoms) in fcc systems ({Al}, {Cu}, {Co}, {Ni} and {Pd}): {Contribution} of first and second order transition states - {ScienceDirect}}, + url = {https://www.sciencedirect.com/science/article/pii/S0925838818332717?via%3Dihub}, + urldate = {2020-02-14}, + file = {Diffusion of interstitial species (H and O atoms) in fcc systems (Al, Cu, Co, Ni and Pd)\: Contribution of first and second order transition states - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\2W724AJV\\S0925838818332717.html:text/html}, +} + +@article{zibrov_experimental_2016, + title = {Experimental determination of the deuterium binding energy with vacancies in tungsten}, + volume = {477}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311505001650}, - doi = {10.1016/j.jnucmat.2004.12.020}, - abstract = {Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5dpa and 500appm He in a temperature range of 120–195°C. Results demonstrate that for all the four kinds of steels, the ductile-to-brittle transition temperature (DBTT) increases with irradiation dose. The difference in the DBTT shifts (ΔDBTT) of the different steels is not significant after irradiation in the SINQ target. The ΔDBTT data from the previous small punch (Δ DBTTSP) and the present Charpy impact (ΔDBTTCVN) tests can be correlated with the expression: Δ DBTTSP=0.4ΔDBTTCVN. All the ΔDBTT data fall into a linear band when they are plotted versus helium concentration. The results indicate that helium effects on the embrittlement of MF steels are significant, particularly at higher concentrations. It suggests that MF steels may not be very suitable for applications at low temperatures in spallation irradiation environments where helium production is high.}, + url = {http://www.sciencedirect.com/science/article/pii/S002231151630174X}, + doi = {10.1016/j.jnucmat.2016.04.052}, + abstract = {Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectroscopy (TDS). In order to obtain a TDS spectrum with a prominent peak corresponding to D release from vacancies, a special procedure comprising damaging of a recrystallized W sample by low fluences of 10 keV/D ions, its annealing, and subsequent low-energy ion implantation, was utilized. This experimental sequence was performed several times in series; the only difference was the TDS heating rate that varied in the range of 0.15–4 K/s. The sum of the D binding energy (Eb) with vacancies and the activation energy for D diffusion (ED) in W was then directly determined from the slope of the Arrhenius-like plot ln(β/Tm2) versus 1/Tm, where β – heating rate and Tm – position of the respective peak in the TDS spectrum. The determined value of Eb + ED was 1.56 ± 0.06 eV.}, language = {en}, - number = {1}, - urldate = {2021-02-10}, + urldate = {2020-02-13}, journal = {Journal of Nuclear Materials}, - author = {Dai, Yong and Marmy, Pierre}, + author = {Zibrov, M. and Ryabtsev, S. and Gasparyan, Yu. and Pisarev, A.}, month = aug, - year = {2005}, - pages = {247--252}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TXR3QMV5\\Dai et Marmy - 2005 - Charpy impact tests on martensiticferritic steels.pdf:application/pdf}, + year = {2016}, + keywords = {Tungsten, TDS, Deuterium, Vacancies, Thermal desorption, Binding energy, Radiation defects}, + pages = {292--297}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\WFCSGD3V\\Zibrov et al. - 2016 - Experimental determination of the deuterium bindin.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\HFE89QV4\\S002231151630174X.html:text/html}, } -@article{testoni_tritium_2019, - series = {{SI}:{SOFT}-30}, - title = {Tritium transport model at breeder unit level for {HCLL} breeding blanket}, - volume = {146}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379619305137}, - doi = {10.1016/j.fusengdes.2019.03.180}, - abstract = {The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses. The present 2D transport model takes into account a single breeder unit located in the outboard equatorial module of the HCLL breeding blanket, which is one of the most loaded modules in normal operating conditions. A multi-physics approach has been adopted considering several physics phenomena, providing for buoyancy effect, temperature fields, tritium generation rate and velocity profile of lead-lithium and coolant. The transport has been modelled considering advection-diffusion of tritium into the lead-lithium eutectic alloy, transfer of tritium from the liquid interface towards the steel (adsorption/desorption), diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant (recombination/desorption), advection-diffusion of diatomic tritium into the coolant. Tritium concentrations, inventories and losses have been derived under the above specified phenomena. In particular, the effect of buoyancy forces on the tritium transport has been implemented and compared with the condition without buoyancy.}, +@article{rougier_ten_2014, + title = {Ten {Simple} {Rules} for {Better} {Figures}}, + volume = {10}, + issn = {1553-7358}, + url = {https://journals.plos.org/ploscompbiol/article?id=10.1371/journal.pcbi.1003833}, + doi = {10.1371/journal.pcbi.1003833}, language = {en}, - urldate = {2021-02-10}, - journal = {Fusion Engineering and Design}, - author = {Testoni, Raffaella and Candido, Luigi and Utili, Marco and Zucchetti, Massimo}, + number = {9}, + urldate = {2020-02-07}, + journal = {PLOS Computational Biology}, + author = {Rougier, Nicolas P. and Droettboom, Michael and Bourne, Philip E.}, month = sep, - year = {2019}, - keywords = {Tritium transport, DEMO, Breeding blanket, HCLL, Buoyancy effect}, - pages = {2319--2322}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EK4EI8T5\\S0920379619305137.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\24MIXHNW\\Testoni et al. - 2019 - Tritium transport model at breeder unit level for .pdf:application/pdf}, + year = {2014}, + keywords = {Software design, Data visualization, Eye movements, Radii, Research design, Seismic signal processing, Software tools, Vision}, + pages = {e1003833}, + file = {Rougier et al. - 2014 - Ten Simple Rules for Better Figures.pdf:D\:\\Logiciels\\data_zotero\\storage\\TC2ZSRL3\\Rougier et al. - 2014 - Ten Simple Rules for Better Figures.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\FVRXHZR8\\article.html:text/html}, } -@incollection{hashimoto_305_2020, - address = {Oxford}, - title = {3.05 - {Radiation} {Effects} in {Ferritic} {Steels} and {Advanced} {Ferritic}-{Martensitic} {Steels}☆}, - isbn = {978-0-08-102866-7}, - url = {https://www.sciencedirect.com/science/article/pii/B978012803581812051X}, - abstract = {The present review begins with a brief introduction to the development of ferritic and ferritic-martensitic steels summarizing the development history in each country. The main thrust is on the development of commercial ferritic steels for core components of fission, fast, and fusion reactors. Hence, the next part of the review introduces the irradiation effects in ferritic and ferritic-martensitic steels, including radiation damage mechanisms of core components in reactors. The irradiation response of ferritic steels with respect to microstructural evolution, swelling, irradiation hardening, irradiation embrittlement, and irradiation creep are highlighted. The main concerns of ferritic steels such as the inferior high temperature irradiation creep and severe embrittlement are addressed. Finally, the development of advanced creep-resistant ferritic steels like ODS steels, for fission and fusion applications are presented. The future trends in the application of ferritic steels in fast and fusion reactor technology are finally summarized.}, +@article{claeys_critical_2020, + title = {Critical assessment of the evaluation of thermal desorption spectroscopy data for duplex stainless steels: {A} combined experimental and numerical approach}, + volume = {186}, + issn = {1359-6454}, + shorttitle = {Critical assessment of the evaluation of thermal desorption spectroscopy data for duplex stainless steels}, + url = {http://www.sciencedirect.com/science/article/pii/S1359645420300112}, + doi = {10.1016/j.actamat.2019.12.055}, + abstract = {The present study evaluates thermal desorption spectroscopy (TDS) data measured for UNS S32205 duplex stainless steel. Variations in the TDS spectra are obtained by electrochemical hydrogen charging for different times and by applying different heating rates for desorption to evaluate the desorption activation energy. Good agreement is found when comparing the experimental TDS curves with the desorption flux based on a numerical diffusion model using a homogeneous average hydrogen diffusion coefficient for the two-phase (ferrite-austenite) duplex microstructure. Trapping cannot be distinguished from the experimental TDS data since hydrogen diffusion in austenite is the rate-determining process during desorption. An average diffusion activation energy of 43.4 kJ/mol is determined from the experiments. Moreover, similar findings are obtained with a finite-element model that includes the heterogeneous hydrogen-related properties of the two phases of this duplex stainless steel.}, language = {en}, - urldate = {2021-02-09}, - booktitle = {Comprehensive {Nuclear} {Materials} ({Second} {Edition})}, - publisher = {Elsevier}, - author = {Hashimoto, Naoyuki and Kasada, Ryuta and Raj, Baldev and Vijayalakshmi, M.}, - editor = {Konings, Rudy J. M. and Stoller, Roger E.}, - month = jan, + urldate = {2020-01-31}, + journal = {Acta Materialia}, + author = {Claeys, L. and Cnockaert, V. and Depover, T. and De Graeve, I. and Verbeken, K.}, + month = mar, year = {2020}, - doi = {10.1016/B978-0-12-803581-8.12051-X}, - keywords = {Evolution, Ferritic/martensitic steel, Hardening, Irradiation, Microstructural}, - pages = {226--254}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DAYZZL9J\\B978012803581812051X.html:text/html}, + keywords = {Hydrogen diffusion, Hydrogen trapping, Diffusion activation energy, Duplex stainless steel, Thermal desorption spectroscopy}, + pages = {190--198}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EA9S9IRD\\Claeys et al. - 2020 - Critical assessment of the evaluation of thermal d.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NVYCIVZQ\\S1359645420300112.html:text/html}, } -@article{chernov_peculiarities_2018, - title = {Peculiarities of helium porosity evolution in the ferritic–martensitic steels produced by spark plasma sintering}, - volume = {16}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179117300820}, - doi = {10.1016/j.nme.2018.07.010}, - abstract = {Oxide dispersion strengthened (ODS) ferritic–martensitic steels are considered as promising structural materials for fusion reactors, as well as for active zone of new generations fast reactors. In this connection, peculiarities of helium porosity formation and gaseous swelling have been investigated in the dispersion-strengthened EP-450 ODS steel with 0.3 and 1 wt.\% Y2O3 dispersant produced by spark plasma sintering (SPS) as compared with the matrix EP-450 steel, EP-450 ODS steel produced using a hot extrusion (HE) as well as reactor austenitic ChS-68 steel. The samples were irradiated by 40-keV Не+ ions at 923 K up to fluence of 5 × 1020 ion/m2. Microstructural investigations of irradiated samples were performed using a transmission electron microscope. It is found that plurality of zones with a very different type of helium porosity and different character of their distribution is developed in steel with 1 wt.\% Y2O3. Such zones are less in steel with 0.3 wt.\% Y2O3 as opposed to matrix EP-450 steel, EP-450 ODS steel obtained by HE, and austenitic ChS-68 reactor steel. It is found in comparing the character of helium porosity formation in the matrix steel EP-450, steel EP-450 ODS (HE) and EP-450 ODS (SPS) that bubbles are developed with a smaller average sizes and, therefore, helium swelling is lower in all ODS steels than that in steel EP-450, but for ODS steel made by SPS, swelling is significantly higher than in ODS steel produced by hot extrusion. At the same time, austenitic steel ChS-68 shows a minimum gaseous swelling for the used conditions of helium ion irradiation. An assumption is made that the extremely nonuniform distribution of helium bubbles (gas filled pores) both in volume and size in SPS steel is associated with the initially highly defect structure, including the residual porosity in 1–3\% as well as a result of strong redistribution of chromium between ferritic grains and grains of tempered martensite during manufacturing of samples.}, +@article{hurley_numerical_2015, + title = {Numerical modeling of thermal desorption mass spectroscopy ({TDS}) for the study of hydrogen diffusion and trapping interactions in metals}, + volume = {40}, + issn = {0360-3199}, + url = {http://www.sciencedirect.com/science/article/pii/S0360319915000051}, + doi = {10.1016/j.ijhydene.2015.01.001}, + abstract = {Deriving the kinetic reaction constants associated with hydrogen diffusion and trapping in metals from thermal desorption mass spectroscopy (TDS) spectra proves to be complicated and the existing analysis methods are subject to debate. This article will provide a brief background of several commonly employed analysis techniques and discuss the necessity of a more complex and rigorous analysis method for the determination of the kinetic constants associated with hydrogen trapping interactions. Furthermore, a numerical simulation method will be proposed using the McNabb \& Foster equations to fit experimental TDS spectra in order to derive both diffusion and trapping/detrapping parameters, including the respective pre-exponential constants and activation energies associated with these interactions in metals.}, language = {en}, - urldate = {2021-02-09}, - journal = {Nuclear Materials and Energy}, - author = {Chernov, I. I. and Staltsov, М. S. and Kalin, B. A. and Bogachev, I. A. and Korshunov, S. N.}, - month = aug, - year = {2018}, - keywords = {Ferritic–martensitic steel, Helium swelling, ODS steels, Oxide-dispersion strengthening, Spark-plasma sintering}, - pages = {249--257}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D6R2D2A7\\S2352179117300820.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PT4G32KD\\Chernov et al. - 2018 - Peculiarities of helium porosity evolution in the .pdf:application/pdf}, + number = {8}, + urldate = {2020-01-28}, + journal = {International Journal of Hydrogen Energy}, + author = {Hurley, Caitlin and Martin, Frantz and Marchetti, Loïc and Chêne, Jacques and Blanc, Christine and Andrieu, Eric}, + month = mar, + year = {2015}, + keywords = {Hydrogen, TDS, Diffusion, Thermal desorption mass spectroscopy, Trapping, Hydrogen embrittlement, Numerical modeling}, + pages = {3402--3414}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PBV2Z33N\\Hurley et al. - 2015 - Numerical modeling of thermal desorption mass spec.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VH6Z2CII\\S0360319915000051.html:text/html}, } -@article{wei_evaluation_2016, - title = {Evaluation of irradiation hardening and microstructure evolution under the synergistic interaction of {He} and subsequent {Fe} ions irradiation in {CLAM} steel}, - volume = {676}, - issn = {0925-8388}, - url = {https://www.sciencedirect.com/science/article/pii/S0925838816307514}, - doi = {10.1016/j.jallcom.2016.03.167}, - abstract = {Sequential dual-ion irradiation is a useful technique for experimental exploration on the synergistic effects of ion accumulation and cascade damage. In this research, the helium-ion accumulation concomitant with displacement damage induced by helium and iron ions irradiation in China low active martensitic (CLAM) steel was studied by ion-irradiation, transmission electron microscopy and nano-indentation technique. The helium bubbles formed under continuous implantation of helium ions at room temperature and the helium dose forming observed bubbles resolved by TEM clearly in CLAM steel is around 0.7 × 1017–1.0 × 1017 He+/cm2 under single 100 keV He+ irradiation. Significant irradiation hardening was observed in the samples with various ion- and dose-irradiations. Positive correlation between the hardening increment and the helium-ion dose has been established in single helium-ion irradiated samples. On the other hand, the subsequent Fe-ion irradiation greatly promoted the formation and growth of helium bubbles as well as dislocation loops in sequential dual-ion irradiated samples. No significant contribution of the subsequent Fe-ion irradiation on the hardness increment was found for the sequential dual-ion irradiated samples. It is suggested that the defects recombination, the combination effects of size and density of defects contribute to the degree of irradiation hardening. The calculated hardness increment based on dispersion strengthening model and the experimental microstructure analysis followed the same trend as the experimental nano-indentation data.}, +@article{backer_multiscale_2017, + title = {Multiscale modelling of the interaction of hydrogen with interstitial defects and dislocations in {BCC} tungsten}, + volume = {58}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Faa8e0c}, + doi = {10.1088/1741-4326/aa8e0c}, + abstract = {In a fusion tokamak, the plasma of hydrogen isotopes is in contact with tungsten at the surface of a divertor. In the bulk of the material, the hydrogen concentration profile tends towards dynamic equilibrium between the flux of incident ions and their trapping and release from defects, either native or produced by ion and neutron irradiation. The dynamics of hydrogen exchange between the plasma and the material is controlled by pressure, temperature, and also by the energy barriers characterizing hydrogen diffusion in the material, trapping and de-trapping from defects. In this work, we extend the treatment of interaction of hydrogen with vacancy-type defects, and investigate how hydrogen is trapped by self-interstitial atom defects and dislocations. The accumulation of hydrogen on dislocation loops and dislocations is assessed using a combination of density functional theory (DFT), molecular dynamics with empirical potentials, and linear elasticity theory. The equilibrium configurations adopted by hydrogen atoms in the core of dislocations as well as in the elastic fields of defects, are modelled by DFT. The structure of the resulting configurations can be rationalised assuming that hydrogen atoms interact elastically with lattice distortions and that they interact between themselves through short-range repulsion. We formulate a two-shell model for hydrogen interaction with an interstitial defect of any size, which predicts how hydrogen accumulates at defects, dislocation loops and line dislocations at a finite temperature. We derive analytical formulae for the number of hydrogen atoms forming the Cottrell atmosphere of a mesoscopic dislocation loop or an edge dislocation. The solubility of hydrogen as a function of temperature, pressure and the density of dislocations exhibits three physically distinct regimes, dominated by the solubility of hydrogen in a perfect lattice, its retention at dislocation cores, and trapping by long-range elastic fields of dislocations.}, language = {en}, - urldate = {2021-02-09}, - journal = {Journal of Alloys and Compounds}, - author = {Wei, Y. P. and Liu, P. P. and Zhu, Y. M. and Wang, Z. Q. and Wan, F. R. and Zhan, Q.}, - month = aug, - year = {2016}, - keywords = {CLAM steel, Ion-irradiation, Irradiation hardening, Microstructure, Nano-indentation, Transmission electron microscopy}, - pages = {481--488}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IIZNZAJP\\S0925838816307514.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\222LPV6L\\Wei et al. - 2016 - Evaluation of irradiation hardening and microstruc.pdf:application/pdf}, + number = {1}, + urldate = {2020-01-21}, + journal = {Nuclear Fusion}, + author = {Backer, A. De and Mason, D. R. and Domain, C. and Nguyen-Manh, D. and Marinica, M.-C. and Ventelon, L. and Becquart, C. S. and Dudarev, S. L.}, + month = nov, + year = {2017}, + pages = {016006}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PPM9WWD9\\Backer et al. - 2017 - Multiscale modelling of the interaction of hydroge.pdf:application/pdf}, } -@article{chen_dislocation_2008, - title = {Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress}, - volume = {56}, - issn = {1359-6454}, - url = {https://www.sciencedirect.com/science/article/pii/S1359645407006350}, - doi = {10.1016/j.actamat.2007.09.016}, - abstract = {The oxide dispersion strengthened (ODS) ferritic steel PM2000, was homogeneously implanted with α-particles under uniaxial tensile stresses ranging from 20 to 250MPa, causing irradiation creep. The irradiation temperatures were 573, 673, and 773K, respectively. Maximum helium concentrations of 3000appm were attained, causing a concurrent displacement dose of approximately 0.75dpa (damage rate about 5×10−6dpas−1). Microstructural changes were studied in detail by transmission electron microscopy (TEM). Two sets of dislocation loops were identified, both interstitial in nature, with Burgers vectors b={\textless}100{\textgreater} and b=½{\textless}111{\textgreater}, and habit planes of (100) and (111), respectively. No influence of stress applied during the irradiation creep tests on loop formation and growth could be detected. TEM investigation also showed the formation of bubbles attached to loops already during implantation at 573K, the formation of bubble–loop complexes at 673K, and Y2O3 particles changing their shape by the attachment of bubbles at 773K.}, +@article{backer_hydrogen_2017, + title = {Hydrogen accumulation around dislocation loops and edge dislocations: from atomistic to mesoscopic scales in {BCC} tungsten}, + volume = {T170}, + issn = {1402-4896}, + shorttitle = {Hydrogen accumulation around dislocation loops and edge dislocations}, + url = {https://doi.org/10.1088%2F1402-4896%2Faa9400}, + doi = {10.1088/1402-4896/aa9400}, + abstract = {In a fusion tokamak, the plasma interacts with the metallic wall and the divertor. Hydrogen isotopes penetrate and diffuse into the material and interact with defects where they are trapped. Neutrons produced by the fusion reactions in the plasma are stopped in the material, creating defects, including vacancy and interstitial clusters, and dislocation loops. The trapping of hydrogen in vacancies has been extensively investigated. In our recent paper (De Backer et al 2017 Nucl. Fusion), we proposed a multi-scale model for H trapping and accumulation around interstitial defects, dislocation loops and dislocation lines. These defects create a long-range elastic field that attracts and may retain H atoms. A two-shell model with a short-range core region and a long-range elastic shell has been parameterized using a database of density functional theory (DFT) calculations. This model gives the number of H atoms forming the Cottrell atmosphere of a defect at finite temperature. In this paper, we present new DFT calculations of large dislocation loops decorated with up to 80 H, and explore our two-shell model in fusion relevant conditions. We conclude that large dislocation loops and edge dislocations can trap a significant number of hydrogen atoms in the core at temperatures up to 800 K, and also in the elastic field if the background hydrogen concentration is high.}, language = {en}, - number = {2}, - urldate = {2021-02-09}, - journal = {Acta Materialia}, - author = {Chen, J. and Jung, P. and Hoffelner, W. and Ullmaier, H.}, - month = jan, - year = {2008}, - keywords = {TEM, Creep, Dislocation, Implantation/irradiation, ODS ferritic steel}, - pages = {250--258}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A83N8HCX\\S1359645407006350.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TLTKA68N\\Chen et al. - 2008 - Dislocation loops and bubbles in oxide dispersion .pdf:application/pdf}, + urldate = {2020-01-21}, + journal = {Physica Scripta}, + author = {Backer, A. De and Mason, D. R. and Domain, C. and Nguyen-Manh, D. and Marinica, M.-C. and Ventelon, L. and Becquart, C. S. and Dudarev, S. L.}, + month = nov, + year = {2017}, + pages = {014073}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\P75275HS\\Backer et al. - 2017 - Hydrogen accumulation around dislocation loops and.pdf:application/pdf}, } -@article{knaster_materials_2016, - title = {Materials research for fusion}, - volume = {12}, - copyright = {2016 Nature Publishing Group}, - issn = {1745-2481}, - url = {https://www.nature.com/articles/nphys3735}, - doi = {10.1038/nphys3735}, - abstract = {Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission reactors. The technological challenges of fusion energy are intimately linked with the availability of suitable materials capable of reliably withstanding the extremely severe operational conditions of fusion reactors. Although fission and fusion materials exhibit common features, fusion materials research is broader. The harder mono-energetic spectrum associated with the deuterium–tritium fusion neutrons (14.1 MeV compared to {\textless}2 MeV on average for fission neutrons) releases significant amounts of hydrogen and helium as transmutation products that might lead to a (at present undetermined) degradation of structural materials after a few years of operation. Overcoming the historical lack of a fusion-relevant neutron source for materials testing is an essential pending step in fusion roadmaps. Structural materials development, together with research on functional materials capable of sustaining unprecedented power densities during plasma operation in a fusion reactor, have been the subject of decades of worldwide research efforts underpinning the present maturity of the fusion materials research programme.}, +@article{gao_implementing_2012, + title = {Implementing the {Nelder}-{Mead} simplex algorithm with adaptive parameters}, + volume = {51}, + issn = {1573-2894}, + url = {https://doi.org/10.1007/s10589-010-9329-3}, + doi = {10.1007/s10589-010-9329-3}, + abstract = {In this paper, we first prove that the expansion and contraction steps of the Nelder-Mead simplex algorithm possess a descent property when the objective function is uniformly convex. This property provides some new insights on why the standard Nelder-Mead algorithm becomes inefficient in high dimensions. We then propose an implementation of the Nelder-Mead method in which the expansion, contraction, and shrink parameters depend on the dimension of the optimization problem. Our numerical experiments show that the new implementation outperforms the standard Nelder-Mead method for high dimensional problems.}, language = {en}, - number = {5}, - urldate = {2021-02-09}, - journal = {Nature Physics}, - author = {Knaster, J. and Moeslang, A. and Muroga, T.}, - month = may, - year = {2016}, - note = {Number: 5 -Publisher: Nature Publishing Group}, - pages = {424--434}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5FJW42KL\\nphys3735.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BN5347RZ\\Knaster et al. - 2016 - Materials research for fusion.pdf:application/pdf}, + number = {1}, + urldate = {2020-01-20}, + journal = {Computational Optimization and Applications}, + author = {Gao, Fuchang and Han, Lixing}, + month = jan, + year = {2012}, + pages = {259--277}, + file = {Springer Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\NBQLQII7\\Gao et Han - 2012 - Implementing the Nelder-Mead simplex algorithm wit.pdf:application/pdf}, } -@article{del_nevo_recent_2019, - series = {{SI}:{SOFT}-30}, - title = {Recent progress in developing a feasible and integrated conceptual design of the {WCLL} {BB} in {EUROfusion} project}, - volume = {146}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379619303503}, - doi = {10.1016/j.fusengdes.2019.03.040}, - abstract = {The water-cooled lithium-lead breeding blanket is in the pre-conceptual design phase. It is a candidate option for European DEMO nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium-lead as breeder-multiplier, pressurized water as coolant and EUROFER as structural material. Current design is based on DEMO 2017 specifications. Two separate water systems are in charge of cooling the first wall and the breeding zone: thermo-dynamic cycle is 295–328 °C at 15.5 MPa. The breeder enters and exits from the breeding zone at 330 °C. Cornerstones of the design are the single module segment approach and the water manifold between the breeding blanket box and the back supporting structure. This plate with a thickness of 100 mm supports the breeding blanket and is attached to the vacuum vessel. It is in charge to withstand the loads due to normal operation and selected postulated initiating events. Rationale and progresses of the design are presented and substantiated by engineering evaluations and analyses. Water and lithium lead manifolds are designed and integrated with the two consistent primary heat transport systems, based on a reliable pressurized water reactor operating experience, and six lithium lead systems. Open issues, areas of research and development needs are finally pointed out.}, +@article{kelley_detection_1999, + title = {Detection and {Remediation} of {Stagnation} in the {Nelder}–{Mead} {Algorithm} {Using} a {Sufficient} {Decrease} {Condition}}, + volume = {10}, + doi = {10.1137/S1052623497315203}, + abstract = {The Nelder--Mead algorithm can stagnate and converge to a nonoptimal point, even for very simple problems. In this note we propose a test for sufficient decrease which, if passed for all iterations, will guarantee convergence of the Nelder--Mead iteration to a stationary point if the objective function is smooth and the diameters of the Nelder--Mead simplices converge to zero. Failure of this condition is an indicator of potential stagnation. As a remedy we propose a new step, which we call an oriented restart, that reinitializes the simplex to a smaller one with orthogonal edges whose orientation is determined by an approximate descent direction from the current best point. We also give results that apply when the objective function is a low-amplitude perturbation of a smooth function. We illustrate our results with some numerical examples.}, + journal = {SIAM Journal on Optimization}, + author = {Kelley, C. T.}, + year = {1999}, + keywords = {Approximation algorithm, Converge, Descent direction, Iteration, Loss function, Numerical analysis, Numerical method, Optimization problem, Perturbation theory, Stationary process}, + pages = {43--55}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\IWHVJUXB\\Kelley - 1999 - Detection and Remediation of Stagnation in the Nel.pdf:application/pdf}, +} + +@book{nocedal_numerical_2006, + address = {New York}, + edition = {2}, + series = {Springer {Series} in {Operations} {Research} and {Financial} {Engineering}}, + title = {Numerical {Optimization}}, + isbn = {978-0-387-30303-1}, + url = {https://www.springer.com/gp/book/9780387303031}, + abstract = {Numerical Optimization presents a comprehensive and up-to-date description of the most effective methods in continuous optimization. It responds to the growing interest in optimization in engineering, science, and business by focusing on the methods that are best suited to practical problems. For this new edition the book has been thoroughly updated throughout. There are new chapters on nonlinear interior methods and derivative-free methods for optimization, both of which are used widely in practice and the focus of much current research. Because of the emphasis on practical methods, as well as the extensive illustrations and exercises, the book is accessible to a wide audience. It can be used as a graduate text in engineering, operations research, mathematics, computer science, and business. It also serves as a handbook for researchers and practitioners in the field. The authors have strived to produce a text that is pleasant to read, informative, and rigorous - one that reveals both the beautiful nature of the discipline and its practical side.}, language = {en}, - urldate = {2021-02-08}, - journal = {Fusion Engineering and Design}, - author = {Del Nevo, A. and Arena, P. and Caruso, G. and Chiovaro, P. and Di Maio, P. A. and Eboli, M. and Edemetti, F. and Forgione, N. and Forte, R. and Froio, A. and Giannetti, F. and Di Gironimo, G. and Jiang, K. and Liu, S. and Moro, F. and Mozzillo, R. and Savoldi, L. and Tarallo, A. and Tarantino, M. and Tassone, A. and Utili, M. and Villari, R. and Zanino, R. and Martelli, E.}, - month = sep, - year = {2019}, - keywords = {DEMO, Breeding blanket, WCLL, EUROfusion}, - pages = {1805--1809}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YK6Y8ZMV\\S0920379619303503.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D5Z7ELJU\\Del Nevo et al. - 2019 - Recent progress in developing a feasible and integ.pdf:application/pdf}, + urldate = {2020-01-20}, + publisher = {Springer-Verlag}, + author = {Nocedal, Jorge and Wright, S.}, + year = {2006}, + doi = {10.1007/978-0-387-40065-5}, + file = {Nocedal et Wright - 2006 - Numerical Optimization.pdf:D\:\\Logiciels\\data_zotero\\storage\\ILVMEVZ3\\Nocedal et Wright - 2006 - Numerical Optimization.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZD24XGZZ\\9780387303031.html:text/html}, } -@article{harutyunyan_deuterium_2021, - title = {Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions}, +@article{juslin_interatomic_2013, + title = {Interatomic potentials for simulation of {He} bubble formation in {W}}, + volume = {432}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311521000714}, - doi = {10.1016/j.jnucmat.2021.152848}, - abstract = {The effect of He-induced defects in tungsten on the efficiency of trapping of deuterium ions in the subsurface layer was studied using thermal desorption spectroscopy (TDS). The W sample was pre-irradiated with 3 keV helium ions at room temperature and various fluences in the range of 1019 – 5 × 1021 He/m2. Then, it was exposed to a probe fluence of 1019 D/m2 of 2 keV D3+ (670 eV/D) ions, and in-situ TDS was performed. The de-trapping energy for D atoms increased with the increase of the He pre-irradiation fluence. On the other hand, a strong decrease in the D retention was observed if the He fluence increased above 1021 He/m2. At the highest He fluence of 5 × 1021 He/m2 deuterium trapping was possible only after partial release of He atoms. By comparison of experimental TDS spectra with modelling, the de-trapping energies of D atoms from various defects were estimated.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311512003820}, + doi = {10.1016/j.jnucmat.2012.07.023}, + abstract = {A new interatomic pair potential for W–He is described, which includes a short range modification to the Ackland–Thetford tungsten potential. Molecular dynamics simulations using these potentials accurately reproduce ab initio results of the formation energies and ground state positions of He point defects and self interstitial atoms in W. Simulations of larger He–vacancy clusters with up to 20 vacancies and 120 He atoms show strong binding of both He and vacancies to He–vacancy clusters for all cluster sizes. For small clusters, the qualitative agreement with ab initio results is good, although the vacancy binding energy is overestimated by the interatomic potential.}, language = {en}, - urldate = {2021-02-08}, + number = {1}, + urldate = {2020-01-15}, journal = {Journal of Nuclear Materials}, - author = {Harutyunyan, Z. and Gasparyan, Yu. and Ryabtsev, S. and Efimov, V. and Ogorodnikova, O. and Pisarev, A. and Kanashenko, S.}, + author = {Juslin, N. and Wirth, B. D.}, month = jan, - year = {2021}, - keywords = {TDS, helium, tungsten, binding energy, deuterium, nuclear fusion, plasma-facing components, thermal desorption}, - pages = {152848}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\P8FQTCV8\\S0022311521000714.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZUCWD5D3\\S0022311521000714.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S38IIUZC\\S0022311521000714.html:text/html}, + year = {2013}, + keywords = {Molecular dynamics}, + pages = {61--66}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2DJ7CAAR\\Juslin et Wirth - 2013 - Interatomic potentials for simulation of He bubble.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GGGDM3IG\\S0022311512003820.html:text/html}, } -@article{zhao_tritium_2019, - title = {Tritium transport analysis for {WCCB} blanket of {CFETR} based on {COMSOL}}, - volume = {140}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379619300523}, - doi = {10.1016/j.fusengdes.2019.01.044}, - abstract = {As for the fusion reactor, tritium has received widely attention due to its self-sufficiency and its influence on the safe operation of the fusion reactor. As a result, quantitative analysis of tritium diffusion, inventory, permeation in the blanket is crucial to the design of tritium fuel circulating system and safety issue. In this study, a two-dimensional model for tritium transport in water cooled ceramic breeder (WCCB) blanket is created, and finite element software COMSOL is used to simulate the tritium transport process. The amount of tritium inventory, the tritium permeation into the coolant, the tritium taken by purge gas and the tritium release are calculated. Besides, the concentration profile of tritium and temperature profile in the blanket are given as well as the sensitivity analysis about the velocity of purge gas is conducted which can offer a reference for the design of tritium extraction system.}, - language = {en}, - urldate = {2021-02-06}, - journal = {Fusion Engineering and Design}, - author = {Zhao, Xueli and Zhang, Bing and Chen, Lei and Huang, Kai and Liu, Songlin}, - month = mar, - year = {2019}, - keywords = {Tritium permeation, COMSOL, Tritium inventory, Tritium release, WCCB blanket}, - pages = {1--10}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PIZNZEA4\\S0920379619300523.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HG87497B\\Zhao et al. - 2019 - Tritium transport analysis for WCCB blanket of CFE.pdf:application/pdf}, +@article{wilson_rare_1974, + title = {Rare gas complexes in tungsten}, + volume = {22}, + issn = {0033-7579}, + url = {https://doi.org/10.1080/00337577408232147}, + doi = {10.1080/00337577408232147}, + abstract = {Specific helium-tungsten defect configurations suggested by Kornelsen to result from ion implantation following irradiation have been calculated. The calculations are atomistic in nature; those interatomic potentials involving the rare gases were determined from fist principles. The divacancy is found to be most stable in the second-neighbor configuration in the pure W lattice, but energetically prefers first-neighbors if it contains a Kr atom. We obtain good agreement with the experimental activation energies although we find certain configurations to differ slightly from those suggested by Kornelsen.}, + number = {1}, + urldate = {2020-01-15}, + journal = {Radiation Effects}, + author = {Wilson, W. D. and Bisson, C. L.}, + month = jan, + year = {1974}, + pages = {63--66}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\F5H4WYSR\\00337577408232147.html:text/html}, } -@article{zhao_3d_2020, - title = {{3D} tritium transport analysis for {WCCB} blanket based on {COMSOL}}, - volume = {151}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379619309019}, - doi = {10.1016/j.fusengdes.2019.111405}, - abstract = {As one of the CFETR candidate blanket schemes, Water-Cooled Ceramic Breeder (WCCB) blanket is being designed and developed by Institute of Plasma Physics, Chinese Academy of Sciences. Considering the safe operation of blanket, especially the radioactivity of tritium, it is crucial to study the tritium performance in the blanket, such as inventory, permeation, tritium taken by purge gas and release, which can likewise provide information for study and design of Tritium Extraction System (TES) and Coolant Purification System (CPS). Based on Finite Element Method (FEM), a more accurate three-dimensional model is set up using COMSOL Multi-physics. The influence of temperature distribution and velocity field of breeder zones on tritium transport is considered in the modelling. Finally, the tritium inventory, tritium permeation, tritium taken by purge gas and tritium release out of the blanket are calculated as well as the sensitivity analysis is conducted.}, - language = {en}, - urldate = {2021-02-06}, - journal = {Fusion Engineering and Design}, - author = {Zhao, Xueli and Ni, Muyi and Nie, Baojie and Zhang, Bing and Chen, Lei and Huang, Kai and Liu, Songlin}, - month = feb, - year = {2020}, - keywords = {Tritium permeation, COMSOL, Tritium inventory, Tritium release, WCCB blanket, 3D model}, - pages = {111405}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DMIGJLU9\\S0920379619309019.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NYFZAL5G\\Zhao et al. - 2020 - 3D tritium transport analysis for WCCB blanket bas.pdf:application/pdf}, +@article{becquart_microstructural_2010, + title = {Microstructural evolution of irradiated tungsten: {Ab} initio parameterisation of an {OKMC} model}, + volume = {403}, + issn = {0022-3115}, + shorttitle = {Microstructural evolution of irradiated tungsten}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311510002448}, + doi = {10.1016/j.jnucmat.2010.06.003}, + abstract = {It is important to develop an understanding of the evolution of W microstructure under the conditions expected in the International Thermonuclear Experimental Reactor as well as the DEMOnstration Power Plant, Modelling techniques can be very helpful in this regards. In this paper, an object kinetic Monte Carlo code has been parameterised on ab initio calculations to model the behaviour of helium atoms implanted in tungsten, in the presence or not of the point defects created during the implantation. The slowing down of atomic helium in tungsten as well as the associated Frenkel Pair production is determined using the Marlowe code and is described in a paper companion to this one. The OKMC simulations indicate that He desorption results from a competition between the formation of mobile clusters and sessile ones, and it is thus very important to model correctly their spatial distributions as well as their properties.}, + language = {en}, + number = {1}, + urldate = {2020-01-15}, + journal = {Journal of Nuclear Materials}, + author = {Becquart, C. S. and Domain, C. and Sarkar, U. and DeBacker, A. and Hou, M.}, + month = aug, + year = {2010}, + keywords = {Density functional theory, Monte Carlo}, + pages = {75--88}, + annote = { +Section 2.3.5 gives the parameterisation of mixed vacancy Helium complexes +"For larger size clusters, no emmission can take place" +}, + file = {Becquart et al. - 2010 - Microstructural evolution of irradiated tungsten .pdf:D\:\\Logiciels\\data_zotero\\storage\\FLCG4BYA\\Becquart et al. - 2010 - Microstructural evolution of irradiated tungsten .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GIIXJ4W9\\S0022311510002448.html:text/html}, } -@article{zinkle_operating_2000, - title = {Operating temperature windows for fusion reactor structural materials}, - volume = {51-52}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379600003203}, - doi = {10.1016/S0920-3796(00)00320-3}, - abstract = {A critical analysis is presented of the operating temperature windows for nine candidate fusion reactor structural materials: four reduced-activation structural materials (oxide-dispersion-strengthened and ferritic/martensitic steels containing 8–12\%Cr, V–4Cr–4Ti, and SiC/SiC composites), copper-base alloys (CuNiBe), tantalum-base alloys (e.g. Ta–8W–2Hf), niobium alloys (Nb–1Zr), and molybdenum and tungsten alloys. The results are compared with the operating temperature limits for Type 316 austenitic stainless steel. Several factors define the allowable operating temperature window for structural alloys in a fusion reactor. The lower operating temperature limit in all body-centered cubic (BCC) and most face-centered cubic (FCC) alloys is determined by radiation embrittlement (decrease in fracture toughness), which is generally most pronounced for irradiation temperatures below ∼0.3 TM where TM is the melting temperature. The lower operating temperature limit for SiC/SiC composites will likely be determined by radiation-induced thermal conductivity degradation, which becomes more pronounced in ceramics with decreasing temperature. The upper operating temperature limit of structural materials is determined by one of four factors, all of which become more pronounced with increasing exposure time: (1) thermal creep (grain boundary sliding or matrix diffusional creep); (2) high temperature He embrittlement of grain boundaries; (3) cavity swelling (particularly important for SiC and Cu alloys); or (4) coolant compatibility/corrosion issues. In many cases, the upper temperature limit will be determined by coolant corrosion/compatibility rather than by thermal creep or radiation effects. The compatibility of the structural materials with Li, Pb–Li, Sn–Li, He and Flibe (Li2BeF4) coolants is summarized.}, +@article{xu_modeling_2010, + title = {Modeling spatially dependent kinetics of helium desorption in {BCC} iron following {He} ion implantation}, + volume = {403}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311510002667}, + doi = {10.1016/j.jnucmat.2010.06.025}, + abstract = {One of the most important tasks in fusion materials research is to study the effect of helium on the microstructure and mechanical property evolution of structural materials. Thermal helium desorption spectrometry (THDS), through measuring the outward He surface flux as a function of temperature (or time), provides indirect information about the kinetics and energetics of helium transport and trapping/detrapping which is important for developing a predictive assessment for the life performance of fusion reactors. Nevertheless, THDS data interpretation is not straightforward, particularly when a broad temperature regime and a high He concentration are concerned. Here we present results from a spatially-dependent rate theory modeling framework in coordination with our previous THDS experiments on single crystal iron implanted with 4He+ ions at 5 or 10keV to fluences of 1018 or 1019 He/m2. The model incorporates both temporally and spatially dependent diffusion, trapping, and detrapping (emission) kinetics for both implantation process and post-implantation thermal annealing. Possible desorption sequences/mechanisms are discussed.}, language = {en}, - urldate = {2021-02-05}, - journal = {Fusion Engineering and Design}, - author = {Zinkle, S. J and Ghoniem, N. M}, - month = nov, - year = {2000}, - keywords = {Fusion energy applications, Structural materials, Temperature windows}, - pages = {55--71}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NZU3HQZ9\\S0920379600003203.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\J4MF3KJW\\Zinkle et Ghoniem - 2000 - Operating temperature windows for fusion reactor s.pdf:application/pdf}, + number = {1}, + urldate = {2020-01-14}, + journal = {Journal of Nuclear Materials}, + author = {Xu, Donghua and Wirth, Brian D.}, + month = aug, + year = {2010}, + keywords = {Cluster dynamics}, + pages = {184--190}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\AB77726G\\Xu et Wirth - 2010 - Modeling spatially dependent kinetics of helium de.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZUAY4876\\S0022311510002667.html:text/html}, } -@article{gabriel_2d_2007, - series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, - title = {A {2D} finite element modelling of tritium permeation for the {HCLL} {DEMO} blanket module}, - volume = {82}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379607004061}, - doi = {10.1016/j.fusengdes.2007.08.001}, - abstract = {A local finite element modelling of the tritium permeation through the HCLL breeder unit cooling plates is presented. The tritium concentration in the helium and in the lithium lead are evaluated by solving partial differential equations governing the tritium balance, the thermal field and the lithium lead velocity field in a simplified 2D-geometrical representation of the breeder unit at the mid-equatorial plan. Using a factorial design at two levels as numerical experiments it is shown that the magnetic field and the natural convection are not relevant for the estimation of the permeation. Moreover, numerical analyses showed a developed concentration boundary layer acting as a mass transfer resistance which is equivalent to a PRF of 30.}, - language = {en}, - number = {15}, - urldate = {2021-02-05}, - journal = {Fusion Engineering and Design}, - author = {Gabriel, F. and Escuriol, Y. and Dabbene, F. and Gastaldi, O. and Salavy, J. F. and Giancarli, L.}, +@article{ortiz_physically_2004, + title = {A physically based model for the spatial and temporal evolution of self-interstitial agglomerates in ion-implanted silicon}, + volume = {96}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.1786678}, + doi = {10.1063/1.1786678}, + number = {9}, + urldate = {2020-01-14}, + journal = {Journal of Applied Physics}, + author = {Ortiz, Christophe J. and Pichler, Peter and Fühner, Tim and Cristiano, Filadelfo and Colombeau, Benjamin and Cowern, Nicholas E. B. and Claverie, Alain}, month = oct, + year = {2004}, + keywords = {Cluster dynamics}, + pages = {4866--4877}, + file = {Ortiz et al. - 2004 - A physically based model for the spatial and tempo.pdf:D\:\\Logiciels\\data_zotero\\storage\\HIAWGXBI\\Ortiz et al. - 2004 - A physically based model for the spatial and tempo.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\48RZTQ2B\\1.html:text/html}, +} + +@article{ortiz_he_2007, + title = {He diffusion in irradiated \${\textbackslash}ensuremath\{{\textbackslash}alpha\}{\textbackslash}text\{{\textbackslash}ensuremath\{-\}\}{\textbackslash}mathrm\{{Fe}\}\$: {An} ab-initio-based rate theory model}, + volume = {75}, + shorttitle = {He diffusion in irradiated \${\textbackslash}ensuremath\{{\textbackslash}alpha\}{\textbackslash}text\{{\textbackslash}ensuremath\{-\}\}{\textbackslash}mathrm\{{Fe}\}\$}, + url = {https://link.aps.org/doi/10.1103/PhysRevB.75.100102}, + doi = {10.1103/PhysRevB.75.100102}, + abstract = {The diffusion of He in irradiated α−Fe is studied using a rate theory model addressing the effect of impurities. Ab initio values for the migration and binding energies of He, He-vacancy complexes, vacancy, and self-interstitial clusters are used to model desorption experiments of He-implanted α−Fe. Using the brute ab initio data yields a significant discrepancy with experimental measurements. On the other hand, good agreement is obtained when the vacancy migration energy is increased from the original ab initio value while the binding energies of vacancies with substitutional and interstitial helium are lowered. The presence of impurities, with carbon being the most likely candidate, is proposed as a justification for these effective energies. Our simulations also provide a detailed description of the diffusion mechanisms of He active under these particular experimental conditions.}, + number = {10}, + urldate = {2020-01-14}, + journal = {Physical Review B}, + author = {Ortiz, C. J. and Caturla, M. J. and Fu, C. C. and Willaime, F.}, + month = mar, year = {2007}, - keywords = {Tritium permeation, MHD, Fusion reactor blanket, Mixed convection}, - pages = {2204--2211}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SA8AISTK\\S0920379607004061.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4U4BT4VN\\Gabriel et al. - 2007 - A 2D finite element modelling of tritium permeatio.pdf:application/pdf}, + keywords = {Cluster dynamics}, + pages = {100102}, + file = {APS Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CUP4HCLQ\\PhysRevB.75.html:text/html;Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\L6DMBTGC\\Ortiz et al. - 2007 - He diffusion in irradiated \$ensuremath alpha te.pdf:application/pdf}, } -@article{abdou_physics_2020, - title = {Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency}, - volume = {61}, - issn = {0029-5515}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/abbf35/meta}, - doi = {10.1088/1741-4326/abbf35}, +@article{jourdan_direct_2011, + title = {Direct simulation of resistivity recovery experiments in carbon-doped \${\textbackslash}upalpha\$-iron}, + volume = {T145}, + issn = {1402-4896}, + url = {https://doi.org/10.1088%2F0031-8949%2F2011%2Ft145%2F014049}, + doi = {10.1088/0031-8949/2011/T145/014049}, + abstract = {We present the simulation of resistivity recovery experiments in carbon-doped α-iron over the whole range of temperatures investigated experimentally (from 77 to 600 K). The binding of carbon atoms with both vacancies and self-interstitial atoms has been investigated by density functional theory calculations. The results have then been used in two complementary kinetic models, event-based kinetic Monte Carlo and cluster dynamics, in order to achieve both accuracy and computational efficiency. We show that good agreement is obtained with experiments and that it is possible to identify the elemental mechanisms responsible for the recovery stages.}, language = {en}, - number = {1}, - urldate = {2021-02-05}, - journal = {Nuclear Fusion}, - author = {Abdou, Mohamed and Riva, Marco and Ying, Alice and Day, Christian and Loarte, Alberto and Baylor, L. R. and Humrickhouse, Paul and Fuerst, Thomas F. and Cho, Seungyon}, - month = nov, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {013001}, - file = {Abdou et al. - 2020 - Physics and technology considerations for the deut.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YM2TGZPV\\Abdou et al. - 2020 - Physics and technology considerations for the deut.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H77WYVLR\\abbf35.html:text/html}, + urldate = {2020-01-14}, + journal = {Physica Scripta}, + author = {Jourdan, T. and Fu, Chu Chun and Joly, L. and Bocquet, J. L. and Caturla, M. J. and Willaime, F.}, + month = dec, + year = {2011}, + keywords = {Cluster dynamics}, + pages = {014049}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\TINCFAIR\\Jourdan et al. - 2011 - Direct simulation of resistivity recovery experime.pdf:application/pdf}, } -@phdthesis{dethloff_modeling_nodate, - title = {Modeling of {Helium} {Bubble} {Nucleation} and {Growth} in {Neutron} {Irradiated} {RAFM} {Steels}}, +@article{li_accumulation_2012, + title = {The {Accumulation} of {He} on a {W} {Surface} {During} {keV}-{He} {Irradiation}: {Cluster} {Dynamics} {Modeling}}, + volume = {14}, + issn = {1009-0630}, + shorttitle = {The {Accumulation} of {He} on a {W} {Surface} {During} {keV}-{He} {Irradiation}}, + url = {https://doi.org/10.1088%2F1009-0630%2F14%2F7%2F13}, + doi = {10.1088/1009-0630/14/7/13}, + abstract = {The accumulation of He on a W surface during keV-He ion irradiation has been simulated using cluster dynamics modeling. This is based mainly on rate theory and improved by involving different types of objects, adopting up-to-date parameters and complex reaction processes, as well as considering the diffusion process along with depth. These new features make the simulated results compare very well with the experimental ones. The accumulation and diffusion processes are analyzed, and the depth and size dependence of the He concentrations contributed by different types of He clusters is also discussed. The exploration of the trapping and diffusion effects of the He atoms is helpful in understanding the evolution of the damages in the near-surface of plasma-facing materials under He ion irradiation.}, language = {en}, - author = {Dethloff, Christian}, - file = {Dethloff - Modeling of Helium Bubble Nucleation and Growth in.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FU3BSUJ6\\Dethloff - Modeling of Helium Bubble Nucleation and Growth in.pdf:application/pdf}, + number = {7}, + urldate = {2020-01-10}, + journal = {Plasma Science and Technology}, + author = {Li, Yonggang and Zhou, Wanghuai and Huang, Liangfeng and Ning, Ronghui and Zeng, Zhi and Ju, Xin}, + month = jul, + year = {2012}, + keywords = {Cluster dynamics}, + pages = {624--628}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\7CDKDCBE\\Li et al. - 2012 - The Accumulation of He on a W Surface During keV-H.pdf:application/pdf}, } -@article{lee_kinetics_2019, - title = {A {Kinetics} of {Hydrogen} {Reduction} of {Nickel} {Oxide} at {Moderate} {Temperature}}, - volume = {25}, - issn = {2005-4149}, - url = {https://doi.org/10.1007/s12540-019-00261-y}, - doi = {10.1007/s12540-019-00261-y}, - abstract = {Nano-metallic nickel powders are highly-valued materials applied in energy, electronic devices and aerospace, which is known to be produced by the gaseous phase reduction method of NiCl2. In the case of a gaseous reduction method, size control is difficult due to the agglomeration of nickel powders. Therefore, a method of producing highly-valued nickel nano-powders from Ni(OH)2 has been proposed. Considering the reduction behavior of bulk nickel oxide has been reported to follow the topo-chemical model. However, reduction behavior of nano-particle is expected to be unknown state. It is necessary to clarify the mechanism of nickel oxide nano-particle reduction. Therefore, in this study, the temperature dependence and particle size dependence on the reduction behavior of from micro scale to nano scale particle was confirmed through TGA experiment. Also, the reduction mechanism of nickel oxide powder was also investigated based on kinetic considerations using the grain topo-chemical model. It was confirmed that the reduction reaction of nickel oxide powder undergoes through the 2nd Avrami model and reduction rate can be expressed by function of temperature and particle size of the powder. Due to the part of the diffusion, the particle size of the powder also affects the rate constant of the reduction reaction.\$\$\{{\textbackslash}text\{g\}\}\_\{\{(\{{\textbackslash}text\{x\}\})\}\} = \{{\textbackslash}text\{k\}\} {\textbackslash}cdot \{{\textbackslash}text\{f\}\}(\{{\textbackslash}text\{d\}\}) {\textbackslash}cdot \{{\textbackslash}text\{t\}\}\$\$g(x)=k·f(d)·t}, +@article{hu_synergistic_2014, + title = {Synergistic effect of helium and hydrogen for bubble swelling in reduced-activation ferritic/martensitic steel under sequential helium and hydrogen irradiation at different temperatures}, + volume = {89}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379614001173}, + doi = {10.1016/j.fusengdes.2014.02.033}, + abstract = {In order to investigate the synergistic effect of helium and hydrogen on swelling in reduced-activation ferritic/martensitic (RAFM) steel, specimens were separately irradiated by single He+ beam and sequential He+ and H+ beams at different temperatures from 250 to 650°C. Transmission electron microscope observation showed that implantation of hydrogen into the specimens pre-irradiated by helium can result in obvious enhancement of bubble size and swelling rate which can be regarded as a consequence of hydrogen being trapped by helium bubbles. But when temperature increased, Ostwald ripening mechanism would become dominant, besides, too large a bubble could become mobile and swallow many tiny bubbles on their way moving, reducing bubble number density. And these effects were most remarkable at 450°C which was the peak bubble swelling temperature for RAMF steel. When temperature was high enough, say above 450, point defects would become mobile and annihilate at dislocations or surface. As a consequence, helium could no longer effectively diffuse and clustering in materials and bubble formation was suppressed. When temperature was above 500, helium bubbles would become unstable and decompose or migrate out of surface. Finally no bubble was observed at 650°C.}, language = {en}, number = {4}, - urldate = {2021-03-19}, - journal = {Metals and Materials International}, - author = {Lee, Dong Soo and Min, Dong Joon}, - month = jul, - year = {2019}, - pages = {982--990}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HYTQCLHN\\Lee et Min - 2019 - A Kinetics of Hydrogen Reduction of Nickel Oxide a.pdf:application/pdf}, + urldate = {2020-01-10}, + journal = {Fusion Engineering and Design}, + author = {Hu, Wenhui and Guo, Liping and Chen, Jihong and Luo, Fengfeng and Li, Tiecheng and Ren, Yaoyao and Suo, Jinping and Yang, Feng}, + month = apr, + year = {2014}, + keywords = {Helium bubbles, Helium/hydrogen synergistic effect, Reduced-activation ferritic/martensitic steel, Swelling}, + pages = {324--328}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PDIX4N9W\\Hu et al. - 2014 - Synergistic effect of helium and hydrogen for bubb.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PYIPCGQ2\\S0920379614001173.html:text/html}, } -@article{zhou_proton_2020, - title = {Proton irradiation-decelerated intergranular corrosion of {Ni}-{Cr} alloys in molten salt}, - volume = {11}, - copyright = {2020 The Author(s)}, - issn = {2041-1723}, - url = {https://www.nature.com/articles/s41467-020-17244-y}, - doi = {10.1038/s41467-020-17244-y}, - abstract = {The effects of ionizing radiation on materials often reduce to “bad news”. Radiation damage usually leads to detrimental effects such as embrittlement, accelerated creep, phase instability, and radiation-altered corrosion. Here we report that proton irradiation decelerates intergranular corrosion of Ni-Cr alloys in molten fluoride salt at 650 °C. We demonstrate this by showing that the depth of intergranular voids resulting from Cr leaching into the salt is reduced by proton irradiation alone. Interstitial defects generated from irradiation enhance diffusion, more rapidly replenishing corrosion-injected vacancies with alloy constituents, thus playing the crucial role in decelerating corrosion. Our results show that irradiation can have a positive impact on materials performance, challenging our view that radiation damage usually results in negative effects.}, +@article{mccarthy_enhanced_2020, + title = {Enhanced fuzzy tungsten growth in the presence of tungsten deposition}, + volume = {60}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Fab6060}, + doi = {10.1088/1741-4326/ab6060}, + abstract = {Using a magnetron sputtering device operating in helium, fibre-form ‘fuzz’ has been grown on tungsten samples in the presence of a significant auxiliary source of depositing tungsten. In this system, fuzzy tungsten was grown over a range of helium ion fluences, , sample temperatures and helium ion energies, but with operator control over the tungsten atom-to-helium ion arrival rate ratio at the sample (from 0.003 to 0.009). In the presence of tungsten deposition, it appears that the fuzz growth has two distinct stages: at low to intermediate helium ion fluence the fuzzy layer thickness follows the expected diffusive law augmented by approximately the ‘effective’ thin film thickness of deposited tungsten; at high fluences the fuzz thickness increases very steeply with . These observations are explained through the increase in the porosity of the fuzzy layer as it reaches thicknesses larger than ∼1 m. It was observed that during the second phase of fuzz growth the thickness was highly dependent on both the sample temperature and the tungsten atom-to-helium ion arrival rate ratio. For the same helium ion exposure, an increase in the sample temperature from 1050 to 1150 K lead to a six-fold increase in the fuzzy layer thickness, whilst increasing the tungsten atom-to-helium ion arrival rate ratio over the full range produced a two-fold increase in the thickness. Microscopy and electron diffraction studies of the grown structures show clearly helium bubbles within polycrystalline tendrils.}, language = {en}, - number = {1}, - urldate = {2021-03-19}, - journal = {Nature Communications}, - author = {Zhou, Weiyue and Yang, Yang and Zheng, Guiqiu and Woller, Kevin B. and Stahle, Peter W. and Minor, Andrew M. and Short, Michael P.}, - month = jul, + number = {2}, + urldate = {2020-01-09}, + journal = {Nuclear Fusion}, + author = {McCarthy, Patrick and Hwangbo, Dogyun and Bilton, Matthew and Kajita, Shin and Bradley, James W.}, + month = jan, year = {2020}, - note = {Number: 1 -Publisher: Nature Publishing Group}, - pages = {3430}, - file = {Zhou et al. - 2020 - Proton irradiation-decelerated intergranular corro.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QXLZI3HJ\\Zhou et al. - 2020 - Proton irradiation-decelerated intergranular corro.pdf:application/pdf}, + keywords = {Fuzz}, + pages = {026012}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\V9QTPMN2\\McCarthy et al. - 2020 - Enhanced fuzzy tungsten growth in the presence of .pdf:application/pdf}, } -@article{candido_novel_2021, - title = {A novel approach to the study of magnetohydrodynamic effect on tritium transport in {WCLL} breeding blanket of {DEMO}}, - volume = {167}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621001101}, - doi = {10.1016/j.fusengdes.2021.112334}, - abstract = {The Water-Cooled Lithium Lead (WCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. Tritium can permeate into the different structural materials, arising potential issues concerning the fuel self-sufficiency and can be lost into the environment with consequent radiological hazard for the population. Within this frame, a tritium transport analysis is fundamental to evaluate tritium retention in LiPb (15.7 at. \% Li) and in the structures and tritium permeation fluxes into the cooling water. To assess this study, a portion of the breeder unit of the outboard equatorial module of the WCLL was modelled. The buoyancy forces and the magnetohydrodynamic (MHD) effect were also included. The final system of partial differential equations was solved with a novel approach through COMSOL Multiphysics. The coupled MHD and heat transfer system of equations was solved performing a transient simulation, that was stopped when the main average variables, temperature and velocity, reached a stable condition. In this way, it was possible to determine the lithium-lead velocity field and to use it as an input for the transport analysis. Tritium transport was modelled by using the input data of tritium generation rate and volumetric power deposition coming from an ad-hoc Monte Carlo simulation realized with MCNP software. Moreover, the transport analysis included advection-diffusion of tritium into the LiPb, transfer of tritium from the liquid interface towards the steel, diffusion of tritium inside the steel, transfer of tritium from the steel towards the coolant, advection-diffusion of diatomic tritium into the coolant.}, - language = {en}, - urldate = {2021-03-22}, - journal = {Fusion Engineering and Design}, - author = {Candido, Luigi and Alberghi, Ciro and Moro, Fabio and Noce, Simone and Testoni, Raffaella and Utili, Marco and Zucchetti, Massimo}, - month = jun, - year = {2021}, - keywords = {Tritium transport, DEMO, WCLL, MHD, MCNP}, - pages = {112334}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CJL333UC\\Candido et al. - 2021 - A novel approach to the study of magnetohydrodynam.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZBH8SFNT\\S0920379621001101.html:text/html}, +@article{liu_new_2018, + title = {New helium bubble growth mode at a symmetric grain-boundary in tungsten: accelerated molecular dynamics study}, + volume = {6}, + issn = {null}, + shorttitle = {New helium bubble growth mode at a symmetric grain-boundary in tungsten}, + url = {https://doi.org/10.1080/21663831.2018.1494637}, + doi = {10.1080/21663831.2018.1494637}, + abstract = {This work, with an emphasis on helium irradiation rates appropriate for fusion-plasma conditions, advances the understanding of helium evolution at grain boundaries in W, an important consideration in the understanding of W as a plasma-facing component. Using accelerated molecular dynamics, helium bubble nucleation and growth at a symmetric Σ5[100](310) tilt grain-boundary in W is studied. The simulations reveal that the growth mode associated with bubble growth at the grain-boundary leads to a suppression of the helium supply to the bubble and hence to arrested growth. Such an unconventional bubble growth mode may dominate in materials with a high density of sinks.}, + number = {9}, + urldate = {2020-01-08}, + journal = {Materials Research Letters}, + author = {Liu, X.-Y. and Uberuaga, B. P. and Perez, D. and Voter, A. F.}, + month = sep, + year = {2018}, + keywords = {Molecular Dynamics}, + pages = {522--530}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Y7THBY4U\\Liu et al. - 2018 - New helium bubble growth mode at a symmetric grain.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7YICGIPV\\21663831.2018.html:text/html}, } -@article{raiman_aggregation_2018, - series = {Special {Section} on "18th {International} {Conference} on {Fusion} {Reactor} {Materials}"}, - title = {Aggregation and data analysis of corrosion studies in molten chloride and fluoride salts}, - volume = {511}, +@article{nguyen_modeling_2019, + title = {Modeling the effects of helium-vacancy clusters on the stress-strain response of a grain boundary in iron by a mechanistic finite element approach informed by molecular dynamics data}, + volume = {526}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311518303957}, - doi = {10.1016/j.jnucmat.2018.07.036}, - abstract = {Corrosion studies in molten fluoride and chloride salts were surveyed, and key data were aggregated into a single dataset. Studies were graphed by salt purity, temperature, sample material, container material, and experimental method (loop, capsule, crucible). To elucidate and quantify the factors that affect corrosion in molten salts, a data analysis using a newly-defined corrosion resistance score and a correlation analysis using techniques borrowed from machine learning were performed. It is shown that salt purity had the strongest correlation with corrosion rates in molten chlorides and fluorides. Data analysis across varied works was inconsistent due to the lack of standardization among molten salt corrosion studies.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311519304106}, + doi = {10.1016/j.jnucmat.2019.151766}, + abstract = {The effects of helium (He)-vacancy clusters on the stress-strain behavior of polycrystalline iron (α-Fe) are investigated by a mechanistic finite element (FE) approach using a continuum damage mechanics (CDM) description of the material behavior informed by molecular dynamics (MD) data. First, MD analyses of a single crystal (loading normal to \{332\} plane) and a bicrystal system containing a Σ11{\textless}110{\textgreater}\{332\} grain boundary (GB) were performed to compute the uniaxial tensile response of an Fe single crystal and a system with a GB. MD results were then used in FE analyses of the same systems to identify parameters for the CDM constitutive relations for the crystal and the traction-separation law for the GB depicted by cohesive elements. Next, a 3D FE model of an α-Fe bicrystal system with an imperfect GB subjected to uniaxial tensile loading was developed. This model includes an equivalent hollow sphere under internal pressure in the middle of the GB to model the effects of pressurized He bubbles at 5 K, room temperature (RT) and 600 K on stress, strain and damage distributions. The radius of the equivalent sphere was determined assuming the presence of two vacancies in the system. Finally, MD stress/strain data of the same bicrystal system with He-vacancy clusters were compared to the corresponding FE results to validate this mechanistic approach that appears to be efficient in terms of computational time. FE model predictions of system strength and fracture strain are in fairly good agreement with the MD results at all three temperatures. Our results show that small and highly pressurized He-vacancy clusters reduce GB strength and fracture strain more significantly at 5 K than at RT and 600 K.}, language = {en}, - urldate = {2021-03-27}, + urldate = {2020-01-08}, journal = {Journal of Nuclear Materials}, - author = {Raiman, Stephen S. and Lee, Sangkeun}, + author = {Nguyen, Ba Nghiep and Kurtz, Richard J. and Gao, Fei}, month = dec, - year = {2018}, - keywords = {Chloride, Concentrated solar, Corrosion, CSP, Fluoride, Molten salt, Molten salt reactor, MSR}, - pages = {523--535}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5JFZKMLB\\S0022311518303957.html:text/html}, + year = {2019}, + keywords = {Molecular Dynamics}, + pages = {151766}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FR2SI8JU\\Nguyen et al. - 2019 - Modeling the effects of helium-vacancy clusters on.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SRASH3CL\\S0022311519304106.html:text/html}, } -@article{delaporte-mathurin_parametric_2021, - title = {Parametric optimisation based on {TDS} experiments for rapid and efficient identification of hydrogen transport materials properties}, - copyright = {All rights reserved}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121000661}, - doi = {10.1016/j.nme.2021.100984}, - abstract = {A novel identification technique of hydrogen transport parameters using FESTIM (Finite Element Simulation of Tritium In Materials) has been demonstrated. FESTIM is a finite element code developed with FEniCS performing hydrogen transport simulations. The trapping parameters (detrapping energies and trap densities) are identified for various materials (Tungsten, Aluminium, EUROFER and Beryllium) by automatically reproducing thermo-desorption experiments. Several optimisation algorithms are tested and the Nelder–Mead algorithm shows the best efficiency. An optimisation test problem with five free parameters took only a few hours to solve whereas optimisation cases with two free parameters took a few minutes. Limitations of this technique are shown and discussed.}, - language = {en}, - urldate = {2021-03-27}, - journal = {Nuclear Materials and Energy}, - author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, - month = mar, - year = {2021}, - keywords = {Finite elements, Automation, Hydrogen transport, Materials, Parametric optimisation}, - pages = {100984}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\96AN4EKH\\S2352179121000661.html:text/html}, +@article{lhuillier_trapping_2011, + series = {Nuclear {Materials} {IV}}, + title = {Trapping and release of helium in tungsten}, + volume = {416}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311510008640}, + doi = {10.1016/j.jnucmat.2010.12.042}, + abstract = {The behavior of tungsten under irradiation and helium implantation is a major stake of the material-related issues of fusion reactors. In this perspective the fate of helium in tungsten was studied by mean of several characterization techniques. The aim of this study is to highlight the trapping mechanisms of helium in tungsten and their correlation with implantation-induced defects. Helium was implanted into tungsten at two different energies, 0.32 and 60keV. The helium was studied as a function of temperature by using nuclear reaction analysis. The migration propensity of helium was correlated with the release rate of helium after annealing at a given temperature. In addition, the helium trapping sites and evolution with post-implantation annealing was investigated using Doppler-Broadening Positron Annihilation Spectroscopy. It has been shown that the release, and so the migration, of helium is guided by the concentration of implantation-induced defects and the nature of the helium traps created during the implantation.}, + language = {en}, + number = {1}, + urldate = {2020-01-08}, + journal = {Journal of Nuclear Materials}, + author = {Lhuillier, P. E. and Belhabib, T. and Desgardin, P. and Courtois, B. and Sauvage, T. and Barthe, M. F. and Thomann, A. L. and Brault, P. and Tessier, Y.}, + month = sep, + year = {2011}, + pages = {13--17}, + file = {Lhuillier et al. - 2011 - Trapping and release of helium in tungsten.pdf:D\:\\Logiciels\\data_zotero\\storage\\6P5R4R4K\\Lhuillier et al. - 2011 - Trapping and release of helium in tungsten.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\AJUXVRFY\\S0022311510008640.html:text/html}, } -@article{hurley_rohydrogene_nodate, - title = {Rôle de l'hydrogène dans la corrosion des alliages base {Nickel} en milieu primaire des {REP} : {Etude} cinétique des mécanismes d'absorption et de piégeage}, - language = {fr}, - author = {Hurley, Caitlin Mae}, - pages = {288}, - file = {Hurley - Rôle de l'hydrogène dans la corrosion des alliages.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QAV764AC\\Hurley - Rôle de l'hydrogène dans la corrosion des alliages.pdf:application/pdf}, +@article{moller_dynamic_2016, + title = {Dynamic outgassing of deuterium, helium and nitrogen from plasma-facing materials under {DEMO} relevant conditions}, + volume = {57}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F0029-5515%2F57%2F1%2F016020}, + doi = {10.1088/0029-5515/57/1/016020}, + abstract = {In confined plasma magnetic fusion devices significant amounts of the hydrogen isotopes used for the fusion reaction can be stored in the plasma-facing materials by implantation. The desorption of this retained hydrogen was seen to follow a t α law with α ≈ −0.7 in tokamaks. For a pulsed fusion reactor this outgassing can define the inter-pulse waiting time. This work presents new experimental data on the dynamic outgassing in ITER grade tungsten exposed under the well-defined conditions of PSI-2 to pure and mixed D2 plasmas. A peak ion flux of 1022 D+ m−2 s is applied for up to 6 h at sample temperatures of up to 900 K. Pure D2 and mixed D2 + He, D2 + N2 and D2 + He + N2 plasmas are applied to the sample at 68 V bias. The D2, He, N outgassing at 293 K and 580 k are observed via in-vacuo quadrupole mass spectrometry covering the range of 40 s–200 000 s after exposure. The outgassing decay follows a single power law with exponents α = −0.7 to −1.1 at 293 K, but at 580 K a drop from α = −0.25 to −2.35 is found. For DEMO a pump-down time to 0.5 mPa in the order of 1–5 h can be expected. The outgassing is in all cases dominated by D2.}, + language = {en}, + number = {1}, + urldate = {2020-01-08}, + journal = {Nuclear Fusion}, + author = {Möller, S. and Matveev, D. and Martynova, Y. and Unterberg, B. and Rasinski, M. and Wegener, T. and Kreter, A. and Linsmeier, Ch}, + month = nov, + year = {2016}, + pages = {016020}, + file = {Möller et al. - 2016 - Dynamic outgassing of deuterium, helium and nitrog.pdf:D\:\\Logiciels\\data_zotero\\storage\\NMFVVGTN\\Möller et al. - 2016 - Dynamic outgassing of deuterium, helium and nitrog.pdf:application/pdf}, } -@article{zhou_water_2021, - title = {A {Water} cooled {Lead} {Ceramic} {Breeder} blanket for {European} {DEMO}}, - volume = {168}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621001733}, - doi = {10.1016/j.fusengdes.2021.112397}, - abstract = {The development of a demonstration fusion power plant (DEMO) is widely considered a crucial step beyond ITER leading toward fusion electricity. In a viable DEMO plant two major functions have to be achieved, namely to breed tritium for fuel self-sufficiency and to extract high-grade heat to allow an efficient electricity production. The breeding blanket is the key component to ensure these two functions. The solid breeder blanket is considered in the design of several ITER Test blankets and DEMO breeding blankets. In Europe, the helium cooled solid breeder blanket, so-called Helium Cooled Pebble Bed (HCPB) blanket, is one of the two driver blanket candidates selected for the European DEMO. In spite of the considerable progress and achievements, several potential issues inherent to the choice of the neutron multiplier and coolant remain with this concept. To overcome these challenges, research activities on an innovative concept (a Water cooled Lead Ceramic Breeder - WLCB), in which Lead/Lead-alloy is used as neutron multiplier, ceramic pebbles as tritium breeder, pressurized sub-cooled water as coolant, are on-going. This concept avoids the potential safety issue (exothermic hydrogen-producing Be-water reaction or PbLi-water reaction in case of water leakage) when Beryllium/Beryllide is used as neutron multiplier or lithium lead is used tritium breeder in a water cooled blanket concept. The neutronics, thermal hydraulics and mechanical performance figures of the above-mentioned innovative blanket concept are presented. This work concludes with possible future work and outlook towards the development of innovative alternative blanket concepts for the European demonstration fusion power plants.}, +@article{das_hardening_2019, + title = {Hardening and {Strain} {Localisation} in {Helium}-{Ion}-{Implanted} {Tungsten}}, + volume = {9}, + issn = {2045-2322}, + url = {http://www.nature.com/articles/s41598-019-54753-3}, + doi = {10.1038/s41598-019-54753-3}, language = {en}, - urldate = {2021-03-26}, - journal = {Fusion Engineering and Design}, - author = {Zhou, Guangming and Lu, Yudong and Hernández, Francisco A.}, - month = jul, - year = {2021}, - keywords = {DEMO, Breeding blanket, Neutronics, Thermal hydraulics, Thermomechanical assessment}, - pages = {112397}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XIYPR9EW\\S0920379621001733.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KVATZY4Y\\Zhou et al. - 2021 - A Water cooled Lead Ceramic Breeder blanket for Eu.pdf:application/pdf}, + number = {1}, + urldate = {2020-01-08}, + journal = {Scientific Reports}, + author = {Das, Suchandrima and Yu, Hongbing and Tarleton, Edmund and Hofmann, Felix}, + month = dec, + year = {2019}, + pages = {18354}, + file = {Das et al. - 2019 - Hardening and Strain Localisation in Helium-Ion-Im.pdf:D\:\\Logiciels\\data_zotero\\storage\\M9XNW9YG\\Das et al. - 2019 - Hardening and Strain Localisation in Helium-Ion-Im.pdf:application/pdf}, } -@article{noauthor_determination_1980, - title = {Determination of deuterium surface recombination rates on stainless steel}, - volume = {93-94}, +@article{dunn_rate_2013, + title = {A rate theory study of helium bubble formation and retention in {Cu}–{Nb} nanocomposites}, + volume = {435}, issn = {0022-3115}, - url = {http://www.sciencedirect.com/science/article/pii/0022311580902196}, - doi = {10.1016/0022-3115(80)90219-6}, - abstract = {The recombination rate coefficient kr (molecules · cm2/atoms2 · s), is experimentally determined by measuring the release rate of deuterium to the gas…}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311512006988}, + doi = {10.1016/j.jnucmat.2012.12.041}, + abstract = {A spatially dependent rate theory model for helium migration, clustering, and trapping on interfaces between Cu and Nb layers is introduced to predict the evolution of the concentrations of He clusters of various sizes during implantation and early annealing. Migration and binding energies of point defects and small clusters in bulk Cu and Nb are found using conjugate gradient minimization and the nudged elastic band method. This model is implemented in a three-dimensional framework and used to predict the relationship between helium bubble formation and the nano-composite microstructure, including interfacial free volume, grain size, and layer thickness. Interstitial and vacancy-like migration of helium is considered. The effects of changing layer thickness and interfacial misfit dislocation density on the threshold for helium bubble nucleation are found to match experiments. Accelerated helium release due to interfaces and grain boundaries is shown to occur only when diffusion rates on interfaces and grain boundaries are greatly increased relative to the bulk material.}, language = {en}, - urldate = {2021-03-24}, + number = {1}, + urldate = {2020-01-08}, journal = {Journal of Nuclear Materials}, - month = oct, - year = {1980}, - note = {Publisher: North-Holland}, - pages = {861--865}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7UPDLW8V\\0022311580902196.html:text/html}, + author = {Dunn, A. Y. and McPhie, M. G. and Capolungo, L. and Martinez, E. and Cherkaoui, M.}, + month = apr, + year = {2013}, + keywords = {Finite Element}, + pages = {141--152}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4DAREWU8\\Dunn et al. - 2013 - A rate theory study of helium bubble formation and.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\J5Q3MQGG\\S0022311512006988.html:text/html}, } -@article{pecovnik_experiments_2021, - title = {Experiments and modelling of multiple sequential {MeV} ion irradiations and deuterium exposures in tungsten}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311521001707}, - doi = {10.1016/j.jnucmat.2021.152947}, - abstract = {Bulk tungsten samples were irradiated sequentially with 20 MeV tungsten ions and exposed to deuterium plasma. The experiments were performed in order to simulate the displacement damage that fusion neutrons will cause in a tungsten plasma-facing component of a future fusion device. To study the influence of the presence of hydrogen isotopes during the creation of displacement damage on the final defect density, tungsten irradiation and deuterium decoration cycles were performed up to three times. Deuterium depth profiling with 3He Nuclear Reaction Analysis and Thermal Desorption Spectroscopy showed that the deuterium concentration increased after each additional tungsten irradiation and deuterium exposure. After the third cycle, the deuterium concentration reached a maximum of 3.6 at.\% at the given plasma exposure temperature of 370 K. We attribute this increase in retention to the stabilization of the displacement damage during the tungsten irradiation by the presence of deuterium. The experimental results were simulated using the MHIMS-R macroscopic rate-equation code, which was recently upgraded with a damage stabilization term to describe experiments where tungsten was irradiated with MeV tungsten ions and simultaneously exposed to low-energy deuterium ions. Using this novel model, it was possible to quantitatively describe also the present results for the sequential irradiation/exposure scheme, with model parameters that were congruent with parameters derived from the simultaneous experiment. Modelling shows that kinetic de-trapping of trapped deuterium takes place during irradiation However, it is not the dominant process that explains defect stabilization. In addition, the model facilitates the extrapolation of present experimental results to an even larger number of sequential tungsten irradiation and deuterium exposure cycles. The model predicts that after about five sequential irradiation and plasma exposure cycles, a stationary state is reached with an associated maximum trapped D concentration of 4.2 at.\% for the given exposure temperature of 370 K.}, +@phdthesis{faney_numerical_2013, + title = {Numerical {Simulations} of {Tungsten} under {Helium} {Irradiation}}, + abstract = {Magnetic confinement fusion is a promising technology for electricity production due to available fuel and low waste products. However, the construction of a nuclear fusion reactor remains +a scientific challenge. One of the main issues is the resistance of the plasma facing materials exposed to very harsh operating conditions. Tungsten is the leading candidate for the divertor, a +crucial plasma facing component. This dissertation focuses on modeling the behavior of tungsten under irradiation conditions relevant to the divertor operations using a multi-scale modeling +approach. In particular, high fluxes of helium ions at low energy impact the divertor and are responsible for changes in the tungsten microstructure such as the formation of helium blisters and +”fuzz”-like structures which can ultimately lead to erosion, degradation of materials performance +and materials failure. +A spatially dependent cluster dynamics model is introduced in order to model the evolution of +the tungsten microstructure under irradiation. This continuum model is based on kinetic rate theory and handles each material defect type independently. Under the assumptions of a low dilute +limit and no spatial correlation between defects, this leads to a large system of non-linear reactiondiffusion equations. Hence, the results addressed in this thesis consist in the determination of the +kinetic parameters for the cluster dynamics model, the construction of a solver which efficiently +deals with the large non-linear system of partial differential equations, the determination of the +applicability of the model to fusion relevant conditions, and the model results for a variety of irradiation conditions. +The input kinetic parameters to the cluster dynamics model are the defects’ diffusion coefficients, binding energies and capture radii. These can be determined using a molecular dynamics and +density functional theory simulations as well as empirical data. The challenge lies in obtaining a +consistent set of kinetic parameters. Therefore, a method to determine the value of the diffusion +coefficients for small helium, interstitial and vacancy defects at various temperatures using only +molecular dynamics simulations is presented. Binding energies are also determined using molecular dynamics, and when combined with the diffusion coefficients they form a consistent set of +kinetic parameters. +An efficient implementation of a parallel solver is presented to deal with the large number of stiff +non linear reaction diffusion equations. The implementation of a SDIRK scheme using a modified version of the SPIKE algorithm gives excellent parallelization results and suggests that this +implementation would also be efficient for an extension of the model to two or three dimensions. +Convergence results for a variety of SDIRK schemes show a convergence order reduction of the +numerical scheme due to the stiffness of the reaction and diffusion terms. +A comparison between simulation results using the cluster dynamics model and experimental results is essential to assess the validity of the model. Comparison with thermal helium desorption +spectrometry experiments at low flux and fluence shows an excellent agreement between simulation and experiments and indicate that the model captures the key physical properties affecting the +evolution of the tungsten microstructure. Further comparison with molecular dynamics simulations +at extremely high fluxes provides an insight in the expected limitations of the model due to surface effects and dilute limit approximations breakdown when applied to fusion relevant conditions. +Results of the model under fusion relevant conditions show the formation of large helium bubbles under the surface at a temperature dependent depth. The results are very sensitive to both +irradiation flux and temperature. At large temperatures, a small concentration of large bubbles +forms first deep under the tungsten surface, and forms a “plug” which moves towards the surface +until eventually the dilute limit approximation breaks down, indicating that the sub-surfaces bubbles become interlinked. At small temperatures, a larger concentration of smaller bubbles forms +close to the surface until eventually surface effects such as bubble bursting are expected to occur. +These results are found to be in good agreement with a similar analytical reaction diffusion model +for fusion relevant conditions. More work is needed to simulate past the dilute limit breakdown +and examine the possibility of taking into account surface effects.}, + school = {UC Berkeley}, + author = {Faney, Thibault}, + year = {2013}, + file = {Faney_berkeley_0028E_13965.pdf:D\:\\Logiciels\\data_zotero\\storage\\W242ND3C\\Faney_berkeley_0028E_13965.pdf:application/pdf}, +} + +@article{fichtl_temperature_2014, + title = {On the {Temperature} {Programmed} {Desorption} of {Hydrogen} from {Polycrystalline} {Copper}}, + volume = {144}, + issn = {1572-879X}, + url = {https://doi.org/10.1007/s10562-014-1384-4}, + doi = {10.1007/s10562-014-1384-4}, + abstract = {Temperature programmed hydrogen desorption (H2-TPD) is a versatile tool to characterize metal surfaces in heterogeneous catalysts. We present a systematic H2-TPD study combined with a kinetic analysis of the H2 desorption process from pure polycrystalline copper and alumina supported copper. The results show that, in contrast to typical Cu/ZnO based methanol synthesis catalysts, the alumina support has no measureable influence on the desorption process and that the copper surface in both catalyst can be accurately described by a theoretically deduced mixture of the low index planes Cu(100), Cu(110), and Cu(111).Graphical Abstract Open image in new window}, language = {en}, - urldate = {2021-03-24}, - journal = {Journal of Nuclear Materials}, - author = {Pečovnik, M. and Schwarz-Selinger, T. and Markelj, S.}, - month = mar, - year = {2021}, - keywords = {Tungsten, Deuterium retention, Damage model, Damage stabilisation, Displacement damage}, - pages = {152947}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JDF4PX5C\\S0022311521001707.html:text/html}, + number = {12}, + urldate = {2019-11-22}, + journal = {Catalysis Letters}, + author = {Fichtl, Matthias B. and Hinrichsen, Olaf}, + month = dec, + year = {2014}, + keywords = {Experiment, Copper, Catalysis, Copper catalysts, Elementary kinetics, Heterogeneous catalysis}, + pages = {2114--2120}, + file = {Fichtl et Hinrichsen - 2014 - On the Temperature Programmed Desorption of Hydrog.pdf:D\:\\Logiciels\\data_zotero\\storage\\3LIA6BLI\\Fichtl et Hinrichsen - 2014 - On the Temperature Programmed Desorption of Hydrog.pdf:application/pdf}, } -@article{wang_thermal_2020, - title = {Thermal damage of tungsten-armored plasma-facing components under high heat flux loads}, - volume = {10}, - copyright = {2020 The Author(s)}, - issn = {2045-2322}, - url = {https://www.nature.com/articles/s41598-020-57852-8}, - doi = {10.1038/s41598-020-57852-8}, - abstract = {Fusion energy is expected as a promising candidate for alternative next generation energy. For fusion reactor, the plasma facing components (PFCs) are the most critical components to achieve this goal. PFCs will suffer severe thermal shock due to repective cyclic high heat flux (HHF) loads. This paper investigates the effects of thermal shock and damage behavior of tungsten armored PFCs under steady, transient and combined thermal loads. The distribution of stress field is analyzed, and crack initiation is predicted using the extended finite element method (XFEM). The unique features of thermal-mechanical behavior of tungsten armored PFCs under simulated service condition are discussed. The dominant factor of the cracking of the tungsten armor is the brittleness of tungsten below ductile-to-brittle transition temperature (DBTT). Under the steady loads, the cracking position is apt to near the interface of tungsten armor and the interlayer, and the threshold of cracking is between 14 MW/m2 and 16 MW/m2. With 6 MW/m2 steady loads, applying 1 ms duration of transient load, the cracking threshold is between 0.2 GW/m2 to 0.4 GW/m2. The depth of cracking increases from 100 um to 500 um with the transient load increasing from 0.4 GW/m2 to 1.0 GW/m2. Researches are useful for the design and structural optimization of tungsten-armored PFCs, and the long-term stable operation of further reactor.}, +@article{mudiyanselage_adsorption_2013, + title = {Adsorption of hydrogen on the surface and sub-surface of {Cu}(111)}, + volume = {139}, + issn = {0021-9606, 1089-7690}, + url = {http://aip.scitation.org/doi/10.1063/1.4816515}, + doi = {10.1063/1.4816515}, language = {en}, - number = {1}, - urldate = {2021-04-01}, - journal = {Scientific Reports}, - author = {Wang, Shuming and Li, Jiangshan and Wang, Ye and Zhang, Xiaofang and Wang, Ruiping and Wang, Yanru and Cao, Jian}, - month = jan, - year = {2020}, - note = {Number: 1 -Publisher: Nature Publishing Group}, - pages = {1359}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NXVP5HK9\\s41598-020-57852-8.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\R9ZREUD2\\Wang et al. - 2020 - Thermal damage of tungsten-armored plasma-facing c.pdf:application/pdf}, + number = {4}, + urldate = {2019-11-22}, + journal = {The Journal of Chemical Physics}, + author = {Mudiyanselage, Kumudu and Yang, Yixiong and Hoffmann, Friedrich M. and Furlong, Octavio J. and Hrbek, Jan and White, Michael G. and Liu, Ping and Stacchiola, Darío J.}, + month = jul, + year = {2013}, + keywords = {Experiment, Copper}, + pages = {044712}, + file = {Mudiyanselage et al. - 2013 - Adsorption of hydrogen on the surface and sub-surf.pdf:D\:\\Logiciels\\data_zotero\\storage\\BAGPXHNW\\Mudiyanselage et al. - 2013 - Adsorption of hydrogen on the surface and sub-surf.pdf:application/pdf}, } -@article{thompson_measuring_2016, - title = {Measuring helium bubble diameter distributions in tungsten with grazing incidence small angle x-ray scattering ({GISAXS})}, - volume = {T167}, - issn = {0031-8949, 1402-4896}, - url = {https://iopscience.iop.org/article/10.1088/0031-8949/2016/T167/014014}, - doi = {10.1088/0031-8949/2016/T167/014014}, - abstract = {Grazing incidence small angle x-ray scattering was performed on tungsten samples exposed to helium plasma in the MAGPIE and Pisces-A linear plasma devices to measure the size distributions of resulting helium nano-bubbles. Nano-bubbles were fitted assuming spheroidal particles and an exponential diameter distribution. These particles had mean diameters between 0.36 and 0.62 nm. Pisces-A exposed samples showed more complex patterns, which may suggest the formation of faceted nano-bubbles or nano-scale surface structures.}, +@article{cao_hydrogen_2018, + title = {Hydrogen adsorption and desorption from {Cu}(111) and {Cu}(211)}, + volume = {20}, + issn = {1463-9084}, + url = {https://pubs.rsc.org/en/content/articlelanding/2018/cp/c8cp03386b}, + doi = {10.1039/C8CP03386B}, + abstract = {We present a combined experimental–theoretical study on structural and coverage dependences of the adsorption and desorption of molecular hydrogen on atomically flat Cu(111) and highly stepped Cu(211) surfaces. For molecules with identical incident energy from supersonic molecular beams, we find a reduced dissociative sticking probability for the stepped surface compared to Cu(111). DFT calculations of activation barriers to dissociation for the clean and partially precovered surfaces, as well as quantitative analysis of TPD spectra, support that the A-type step of the (211) surface causes an upward shift in activation barriers to dissociation and lowering of the desorption barrier. The new data allow us to determine low sticking probabilities at conditions where King and Wells measurements fail to determine the reactivity. They are also fully consistent with the unexpected observation that monoatomic steps on a surface lower the reactivity toward the dissociation of a diatomic molecule.}, language = {en}, - urldate = {2021-04-01}, - journal = {Physica Scripta}, - author = {Thompson, M and Kluth, P and Doerner, R P and Kirby, N and Riley, D and Corr, C S}, - month = feb, - year = {2016}, - pages = {014014}, - file = {Thompson et al. - 2016 - Measuring helium bubble diameter distributions in .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7D7FLYTE\\Thompson et al. - 2016 - Measuring helium bubble diameter distributions in .pdf:application/pdf}, + number = {35}, + urldate = {2019-11-22}, + journal = {Physical Chemistry Chemical Physics}, + author = {Cao, Kun and Füchsel, Gernot and Kleyn, Aart W. and Juurlink, Ludo B. F.}, + month = sep, + year = {2018}, + keywords = {Experiment, Copper}, + pages = {22477--22488}, + file = {Cao et al. - 2018 - Hydrogen adsorption and desorption from Cu(111) an.pdf:D\:\\Logiciels\\data_zotero\\storage\\8LEAR3YL\\Cao et al. - 2018 - Hydrogen adsorption and desorption from Cu(111) an.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\BUB7QRYW\\c8cp03386b.html:text/html}, } -@article{chen_deuterium_2021, - title = {Deuterium transport and retention properties of representative fusion blanket structural materials}, - volume = {549}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311521001288}, - doi = {10.1016/j.jnucmat.2021.152904}, - abstract = {Reduced activation ferritic-martensitic (RAFM) steels have been developed for decades for use as fusion blanket structural materials, and have advantages in both mechanical properties and irradiation resistance following careful engineering of the microstructure. However, the hydrogen isotope behavior in these proposed fusion structural materials is not well understood, but is important to assess since it impacts the fusion reactor safety and self-sufficient tritium fuel cycle. In this work, we investigated deuterium transport and retention in representative advanced RAFM steels, including castable nanostructured alloys (CNAs), and oxide-dispersion-strengthened (ODS) steels. A gas-driven permeation (GDP) system was used to measure the permeability, diffusivity and solubility of the studied materials, covering the temperature range from 623 K to 873 K, and the loading pressures from 1.8×104 to 1.0×105 Pa. The results indicated that the deuterium permeability has little material dependence. In contrast, the deuterium diffusivity of the studied materials showed significant variation. The deuterium diffusivity in ODS steels is one order of magnitude lower than that in RAFM steels and CNAs, and correspondingly, have an effective solubility that is 2–10 times larger than RAFM steels and CNAs. In addition, thermal desorption spectroscopy (TDS) measurements were performed to assess the deuterium retention and desorption of these materials following a static thermal deuterium charging at 723 Kfor 1 hour under the deuterium pressure of 1.0×105Pa. It was found that ODS steels exhibit the highest deuterium retention and have broader desorption peaks. Microstructural features contributing to deuterium retention and impacting deuterium transport are discussed to rationalize the observed deuterium behavior in the studied RAFM steels.}, +@article{amador_effect_2019, + title = {The {Effect} of {Pulsed} {Current} and {Organic} {Additives} on {Hydrogen} {Incorporation} in {Electroformed} {Copper} {Used} in {Ultrahigh} {Vacuum} {Applications}}, + volume = {166}, + issn = {0013-4651, 1945-7111}, + url = {http://jes.ecsdl.org/content/166/10/D366}, + doi = {10.1149/2.1211908jes}, + abstract = {The presence of hydrogen in electroformed copper from two different acidic copper sulfate solutions was evaluated: an additive-free solution and a solution including a sugar. D-xylose addition is found to inhibit H incorporation and allows the use of higher cathodic pulses before the copper diffusion limited range starts. TDS experiments show that hydrogen is trapped in the copper samples in two different forms. Hydrogen diffused from copper vacancies was found on all samples at an outgassing temperature of around 450°C. For samples with long pulse times, an additional H2 outgassing peak was found at around 600°C. XRD measurements allowed us to determine the preferential orientation of the plated samples and to monitor lattice parameter evolution with increasing temperature.}, language = {en}, - urldate = {2021-03-31}, - journal = {Journal of Nuclear Materials}, - author = {Chen, Ze and Hu, Xunxiang and Ye, Minyou and Wirth, Brian D.}, - month = jun, - year = {2021}, - keywords = {Deuterium retention, Deuterium transport, Reduced activation ferritic-martensitic steels}, - pages = {152904}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G8R2BGGL\\S0022311521001288.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YSJHYIX3\\Chen et al. - 2021 - Deuterium transport and retention properties of re.pdf:application/pdf}, + number = {10}, + urldate = {2019-11-22}, + journal = {Journal of The Electrochemical Society}, + author = {Amador, L. Lain and Rolet, J. and Doche, M.-L. and Massuti-Ballester, P. and Gigandet, M.-P. and Moutarlier, V. and Taborelli, M. and Ferreira, L. M. A. and Chiggiato, P. and Hihn, J.-Y.}, + month = jan, + year = {2019}, + keywords = {Experiment, Copper}, + pages = {D366--D373}, + file = {Amador et al. - 2019 - The Effect of Pulsed Current and Organic Additives.pdf:D\:\\Logiciels\\data_zotero\\storage\\4ALGFT57\\Amador et al. - 2019 - The Effect of Pulsed Current and Organic Additives.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KWEGE895\\D366.html:text/html}, } -@article{valles_temperature_2017, - title = {Temperature dependence of underdense nanostructure formation in tungsten under helium irradiation}, - volume = {490}, +@article{anderl_hydrogen_1990, + title = {Hydrogen transport behavior of metal coatings for plasma-facing components}, + volume = {176-177}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311516312478}, - doi = {10.1016/j.jnucmat.2017.04.021}, - abstract = {Recently, tungsten has been found to form a highly underdense nanostructured morphology (“W fuzz”) when bombarded by an intense flux of He ions, but only in the temperature window 900–2000 K. Using object kinetic Monte Carlo simulations (pseudo-3D simulations) parameterized from first principles, we show that this temperature dependence can be understood based on He and point defect clustering, cluster growth, and detrapping reactions. At low temperatures ({\textless}900 K), fuzz does not grow because almost all He is trapped in very small He-vacancy clusters. At high temperatures ({\textgreater}2300 K), all He is detrapped from clusters, preventing the formation of the large clusters that lead to fuzz growth in the intermediate temperature range.}, - language = {en}, - urldate = {2021-03-30}, - journal = {Journal of Nuclear Materials}, - author = {Valles, G. and Martin-Bragado, I. and Nordlund, K. and Lasa, A. and Björkas, C. and Safi, E. and Perlado, J. M. and Rivera, A.}, - month = jul, - year = {2017}, - keywords = {Tungsten, Fuzz nanostructures, Helium irradiation, OKMC simulations, Temperature}, - pages = {108--114}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3GN6KZMT\\S0022311516312478.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PXEATDJS\\Valles et al. - 2017 - Temperature dependence of underdense nanostructure.pdf:application/pdf}, + url = {http://www.sciencedirect.com/science/article/pii/0022311590901279}, + doi = {10.1016/0022-3115(90)90127-9}, + abstract = {Plasma-facing components for experimental and commercial fusion reactor studies may include cladding or coatings of refractory metals like tungsten on metallic structural substrates such as copper, vanadium alloys and austenitic stainless steel. Issues of safety and fuel economy include the potential for inventory buildup and permeation of tritium implanted into the plasma-facing surface. This paper reports on laboratory-scale studies with 3 keV D+3 ion beams to investigate the hydrogen transport behavior in tungsten coatings on substrates of copper. These experiments entailed measurements of the deuterium re-emission and permeation rates for tungsten, copper, and tungsten-coated copper specimens at temperatures ranging from 638 to 825 K and implanting particle fluxes of approximately 5 × 1019 D/m2 s. Diffusion constants and surface recombination coefficients with enhancement factors due to sputtering were obtained from these measurements. These data may be used in calculations to estimate permeation rates and inventory buildups for proposed diverter designs.}, + language = {en}, + urldate = {2019-11-22}, + journal = {Journal of Nuclear Materials}, + author = {Anderl, R. A. and Holland, D. F. and Longhurst, G. R.}, + month = dec, + year = {1990}, + keywords = {Experiment, Copper}, + pages = {683--689}, + file = {Anderl et al. - 1990 - Hydrogen transport behavior of metal coatings for .pdf:D\:\\Logiciels\\data_zotero\\storage\\9N46YH75\\Anderl et al. - 1990 - Hydrogen transport behavior of metal coatings for .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\A94XN6LD\\0022311590901279.html:text/html}, } -@article{goldstein_diffusion_2007, - title = {Diffusion {Limited} {Reactions}}, - volume = {67}, - issn = {0036-1399}, - url = {https://www.jstor.org/stable/40233434}, - abstract = {Changes to the relative separation of molecules or other interacting species on account of diffusion accompany their associative or dissociative reaction. The molecules are symbolized, for two distinct types, A,B, by the relations A+B =AB, and, if [A], [B], and [AB] denote the corresponding densities, the equation {\textless}tex-math{\textgreater}\$\{d {\textbackslash}over \{dt\}\}[AB] = K\_ + [A][B]\${\textless}/tex-math{\textgreater} specifies an associative process with forward rate constant k₊. An approximate version of the preceding takes the form of a linear differential equation, which can be employed to obtain significant estimates for both k₊ and the flux function d[AB]/dt. Such estimates are presented in different circumstances, including the localization of A,B on a common planar surface or their distribution in space, and also when the domain of A is a half space whereas that of B is a bounding planar surface. It proves advantageous to reformulate the last, a mixed boundary value problem, in terms of a linear integral equation. Biological applications are discussed, including the mechanism for the observed phosphorylation of proteins in resting cells and the incipience of phototransduction in rod photoreceptors.}, +@article{wilson_hydrogen_1987, + title = {Hydrogen isotope retention and release from copper}, + volume = {5}, + issn = {0734-2101}, + url = {https://avs.scitation.org/doi/10.1116/1.574444}, + doi = {10.1116/1.574444}, number = {4}, - urldate = {2021-04-02}, - journal = {SIAM Journal on Applied Mathematics}, - author = {Goldstein, Byron and Levine, Harold and Torney, David}, - year = {2007}, - note = {Publisher: Society for Industrial and Applied Mathematics}, - pages = {1147--1165}, + urldate = {2019-11-22}, + journal = {Journal of Vacuum Science \& Technology A}, + author = {Wilson, K. L. and Causey, R. A. and Baskes, M. I. and Kamperschroer, J.}, + month = jul, + year = {1987}, + keywords = {Experiment, Copper}, + pages = {2319--2324}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PSWXRMKX\\1.html:text/html}, } -@article{tassone_computational_2021, - title = {Computational {MHD} analyses in support of the design of the {WCLL} {TBM} breeding zone}, - volume = {170}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621003112}, - doi = {10.1016/j.fusengdes.2021.112535}, - abstract = {The Water-Cooled Lithium Lead (WCLL) is a blanket concept pursued in the framework of Test Blanket Module (TBM) campaign in ITER. Even if the liquid metal is circulated slowly in the component, magnetohydrodynamic (MHD) pressure losses are still expected to be significant. The aim of this paper is to assess the MHD pressure losses in the TBM frontal part, also called Breeding Zone (BZ). There, important contributions are caused by the manifold interface, the presence of cooling pipes obstructing the fluid movement, a sharp hairpin bend, and non-uniform wall thickness of the walls. Direct numerical simulation of 2D and 3D MHD flows is used to estimate the head loss for each one of these elements. A scaling law is derived to allow quick estimate of the pressure loss from reference parameters. The main contribution to the head loss is caused by the windows that connect the BZ with the manifold.}, +@article{penalva_interaction_2012, + title = {Interaction of {Copper} {Alloys} with {Hydrogen}}, + url = {https://www.intechopen.com/books/copper-alloys-early-applications-and-current-performance-enhancing-processes/interaction-of-copper-alloys-with-hydrogen}, + doi = {10.5772/34469}, + abstract = {Open access peer-reviewed chapter}, language = {en}, - urldate = {2021-04-06}, - journal = {Fusion Engineering and Design}, - author = {Tassone, Alessandro and Caruso, Gianfranco}, - month = sep, - year = {2021}, - keywords = {ITER, TBM, Liquid metals, Magnetohydrodynamics (MHD), Pressure drop, WCLL blanket}, - pages = {112535}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZK4SLJ89\\Tassone et Caruso - 2021 - Computational MHD analyses in support of the desig.pdf:application/pdf}, + urldate = {2019-10-07}, + journal = {Copper Alloys - Early Applications and Current Performance - Enhancing Processes}, + author = {Peñalva, I. and Alberro, G. and Legarda, F. and Esteban, G. A. and Riccardi, B.}, + month = mar, + year = {2012}, + keywords = {Experiment, Copper}, + file = {Peñalva et al. - 2012 - Interaction of Copper Alloys with Hydrogen.pdf:D\:\\Logiciels\\data_zotero\\storage\\585MS3D4\\Peñalva et al. - 2012 - Interaction of Copper Alloys with Hydrogen.pdf:application/pdf}, } -@article{utili_development_2021, - title = {Development of anti-permeation and corrosion barrier coatings for the {WCLL} breeding blanket of the {European} {DEMO}}, - volume = {170}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621002295}, - doi = {10.1016/j.fusengdes.2021.112453}, - abstract = {Tritium permeation from breeder material to the Water Coolant System (WCS) in Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the technological issues to be solved in the design of the European DEMO. Since the tritium extraction from the Water Coolant System is more challenging and expensive than the extraction from the eutectic alloy PbLi, it is mandatory to use of a protective coating on the blanket wall to minimize the permeation rate. Moreover, a protective coating can prevent the corrosion of EUROFER steel by the action of PbLi. alumina-based coatings are considered as reference for barriers thanks to their good chemical compatibility with the PbLi alloy and their capability to reduce permeation. Three coating technologies were selected in the frame of the EUROfusion project: electrochemical ECX (chemical deposition) process, Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) coating. The coatings were developed and optimized in order to satisfy the design requirements of good mechanical compatibility with steels, strong adhesion, corrosion compatibility in PbLi at relevant BB design conditions and a Permeation Reduction Factor at least of 200 under neutron irradiation. The present paper aims to describe the status of the technologies and the main results obtained. The final objectives of the R\&D activities are to demonstrate the applicability of the coating to WCLL BB and therefore the scale-up of the technologies from laboratory scale to the BB scale.}, +@article{lloyd_surface_1997, + title = {Surface and bulk interactions of hydrogen with copper}, + volume = {119}, + issn = {01694332}, + url = {https://linkinghub.elsevier.com/retrieve/pii/S0169433297001797}, + doi = {10.1016/S0169-4332(97)00179-7}, + abstract = {The permeation of deuterium through a 25 /{\textasciitilde}m Cu foil was investigated using an atomic deuterium source. The diffusivity of deuterium in Cu at temperatures from 350-550 K was measured. Diffusivities observed in this study are in good agreement with reported values observed at higher temperatures (circa 800-1000 K). Use of an atomic deuterium source provided high internal pressures and superinventory effects analogous to those reported for various hydrogen-metal systems. Data collected in this study together with thermal desorption studies have been used to develop a comprehensive Lennard-Jones potential model for the Cu/D system. © 1997 Elsevier Science B.V.}, language = {en}, - urldate = {2021-04-03}, - journal = {Fusion Engineering and Design}, - author = {Utili, Marco and Bassini, Serena and Cataldo, Sebastiano and Di Fonzo, Fabio and Kordac, Michal and Hernandez, Teresa and Kunzova, Klara and Lorenz, Julia and Martelli, Daniele and Padino, Boris and Moroño, Alejandro and Tarantino, Mariano and Schroer, Carsten and Spagnuolo, Gandolfo Alessandro and Vala, Ladislav and Vanazzi, Matteo and Venturini, Alessandro}, - month = sep, - year = {2021}, - keywords = {Tritium permeation, DEMO, Irradiation, Corrosion, Alumina coating, PbLi}, - pages = {112453}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GBKYI6VX\\S0920379621002295.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DG4E4YVN\\Utili et al. - 2021 - Development of anti-permeation and corrosion barri.pdf:application/pdf}, + number = {3-4}, + urldate = {2019-11-22}, + journal = {Applied Surface Science}, + author = {Lloyd, Peter B. and Kress, John W. and Tatarchuk, Bruce J.}, + month = oct, + year = {1997}, + keywords = {Experiment, Copper}, + pages = {275--287}, + file = {Lloyd et al. - 1997 - Surface and bulk interactions of hydrogen with cop.pdf:D\:\\Logiciels\\data_zotero\\storage\\U8TGZYZH\\Lloyd et al. - 1997 - Surface and bulk interactions of hydrogen with cop.pdf:application/pdf}, } -@article{xie_new_2017, - title = {A new loop-punching mechanism for helium bubble growth in tungsten}, - volume = {141}, - issn = {1359-6454}, - url = {https://www.sciencedirect.com/science/article/pii/S1359645417307395}, - doi = {10.1016/j.actamat.2017.09.005}, - abstract = {Growth of helium (He) bubbles with different initial sizes in tungsten (W) has been investigated by performing molecular dynamics simulations. Based on the simulation results a new loop punching mechanism for the large helium bubble growth is proposed. Different from the growth of small-size He bubbles by pushing out self-interstitial atoms and then rearranging into a prismatic dislocation loop, a large-size bubble grows by pushing out a dislocation, subsequently cross-slipping of its screw components and finally evolving into a prismatic dislocation loop. Such dislocations may react with each other to form a dislocation net around the bubble rather than to convert to prismatic dislocation loops.}, +@article{perkins_permeation_1972, + title = {Permeation and diffusion of hydrogen in ceramvar, copper, and ceramvar-copper laminates}, + volume = {76}, + copyright = {Copyright © 1972 Wiley‐VCH Verlag GmbH \& Co. KGaA, Weinheim}, + issn = {0005-9021}, + url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/bbpc.19720760866}, + doi = {10.1002/bbpc.19720760866}, language = {en}, - urldate = {2021-04-03}, - journal = {Acta Materialia}, - author = {Xie, Hongxian and Gao, Ning and Xu, Ke and Lu, Guang-Hong and Yu, Tao and Yin, Fuxing}, - month = dec, - year = {2017}, - keywords = {He bubble growth}, - pages = {10--17}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XTJN2RDR\\S1359645417307395.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZPM9PHAM\\Xie et al. - 2017 - A new loop-punching mechanism for helium bubble gr.pdf:application/pdf}, + number = {8}, + urldate = {2019-11-22}, + journal = {Berichte der Bunsengesellschaft für physikalische Chemie}, + author = {Perkins, W. G. and Begeal, D. R.}, + year = {1972}, + keywords = {Experiment, Copper}, + pages = {863--863}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VGVPLNVQ\\bbpc.html:text/html}, } -@article{sorbom_arc_2015, - title = {{ARC}: {A} compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets}, - volume = {100}, - issn = {0920-3796}, - shorttitle = {{ARC}}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379615302337}, - doi = {10.1016/j.fusengdes.2015.07.008}, - abstract = {The affordable, robust, compact (ARC) reactor is the product of a conceptual design study aimed at reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ∼200–250MWe tokamak reactor with a major radius of 3.3m, a minor radius of 1.1m, and an on-axis magnetic field of 9.2T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This allows the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Qp≈13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ∼63\%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ∼23T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25MW of lower hybrid and 13.6MW of ion cyclotron fast wave power. The resulting efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio≥1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.}, +@article{magnusson_self-diffusion_2013, + title = {Self-diffusion and impurity diffusion of hydrogen, oxygen, sulphur and phosphorus in copper}, + abstract = {A study on the mobility of hydrogen, oxygen, sulphur, and phosphorus in copper has been made. +In addition, the self-diffusion of copper has also been studied. Literature data has been reviewed, +and used to evaluate the temperature expressions of the diffusion coefficients of these elements in +copper. The interstitial elements oxygen and hydrogen have been described by a single temperature +expression in the whole temperature range, whereas the substitutional elements copper, sulphur, +and phosphorus have been modelled according to lattice diffusion at high temperatures and grain +boundary diffusion at low temperatures. +Sulphur, phosphorus, and copper are believed to be nearly immobile within the crystalline grains +at low temperature, even for time periods up to 100,000 years. On the other hand, in the grain +boundaries these elements can diffuse and an upper limit estimate of the possible diffusion distance +has been made. At room temperature sulphur can diffuse up to 5 cm for 100,000 years, whereas both +phosphorus and copper requires more than 1,000 000 years to diffuse the same distance. The oxygen +atom shows a similar mobility, although it is interstitially diffusing through the grains. However, +since both oxygen and sulphur have a very low solubility any measureable mass transport of these +elements will never take place at low temperatures. They will instead form oxides and sulphides in +the material. +Hydrogen is a mobile element, and will be able to diffuse through 5 cm of copper during a time period +of 1,000 years at room temperature. The diffusion of hydrogen in copper is experimentally well studied +down to room temperature. By combining the evaluated hydrogen diffusion coefficient with the +thermodynamically calculated hydrogen content in solid solution the permeability of hydrogen can be +explained. This can be used to explain the mass-transport of hydrogen for different times, temperatures, +and hydrogen activities (pressures).}, language = {en}, - urldate = {2021-04-16}, - journal = {Fusion Engineering and Design}, - author = {Sorbom, B. N. and Ball, J. and Palmer, T. R. and Mangiarotti, F. J. and Sierchio, J. M. and Bonoli, P. and Kasten, C. and Sutherland, D. A. and Barnard, H. S. and Haakonsen, C. B. and Goh, J. and Sung, C. and Whyte, D. G.}, - month = nov, - year = {2015}, - keywords = {Tokamak, Compact pilot reactor, Fusion nuclear science facility, High magnetic field, High-field launch, Liquid immersion blanket, Superconducting joints}, - pages = {378--405}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ID5WW77S\\Sorbom et al. - 2015 - ARC A compact, high-field, fusion nuclear science.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CDC5ZJ83\\S0920379615302337.html:text/html}, + author = {Magnusson, Hans and Frisk, Karin}, + month = dec, + year = {2013}, + keywords = {Experiment, Copper}, + pages = {33}, + file = {Magnusson et Frisk - Self-diffusion and impurity diffusion of hydrogen,.pdf:D\:\\Logiciels\\data_zotero\\storage\\4NKYXHFM\\Magnusson et Frisk - Self-diffusion and impurity diffusion of hydrogen,.pdf:application/pdf}, } -@article{sorbom_liquid_2012, - title = {Liquid immersion blanket design for use in a compact modular fusion reactor}, - url = {http://adsabs.harvard.edu/abs/2012APS..DPPUP8055S}, - abstract = {Traditional tritium breeding blankets in fusion reactor designs include a large amount of structural material. This results in complex -engineering requirements, complicated sector maintenance, and marginal tritium breeding ratios (TBR). We present a conceptual design of a fully liquid blanket. To maximize tritium breeding volume, the vacuum vessel is completely immersed in a continuously recycled FLiBe blanket, with the exception of small support posts. FLiBe has a wide liquid -temperature window (459 C to 1430 C), low electrical conductivity to minimize MHD effects, similar thermal/fluid characteristics to water, and is chemically inert. While tritium breeding with FLiBe in -traditional blankets is poor, we use MCNP neutronics analysis to show that the immersion blanket design coupled with a beryllium neutron multiplier results in TBR {\textgreater} 1. FLiBe is shown to be a sufficient radiation shield for the toroidal field magnets and can be used as a coolant for the vacuum vessel and divertor, allowing for a simplified single-phase, low-pressure, single-fluid cooling scheme. When coupled with a high-field compact reactor design, the immersion blanket -eliminates the need for complex sector maintenance, allows the vacuum vessel to be a replaceable component, and reduces financial cost.}, - urldate = {2021-04-16}, - author = {Sorbom, Brandon and Ball, Justin and Barnard, Harold and Haakonsen, Christian and Hartwig, Zachary and Olynyk, Geoffrey and Sierchio, Jennifer and Whyte, Dennis}, - month = oct, - year = {2012}, - note = {Conference Name: APS Meeting Abstracts}, - pages = {UP8.055}, +@article{sakamoto_electrochemical_1982, + title = {The {Electrochemical} {Determination} of {Diffusivity} and {Solubility} of {Hydrogen} in {Copper}}, + volume = {46}, + doi = {10.2320/jinstmet1952.46.3_285}, + abstract = {The diffusivity and solubility of hydrogen in both annealed and as-cold-rolled copper were determined at room temperature by means of the electrochemical permeation method under the galvanostatic charging condition. Results obtained were as follows:(1) The observed build-up transient of hydrogen permeation through Cu foil specimens coincided with the theoretical transient which is the boundary condition of constant hydrogen concentration directly beneath the cathodic surface. Furthermore, the specimen thickness dependence of the steady state permeation current density was examined and consequently, the diffusion of hydrogen through the Cu foil in the permeation process was the rate determining step.(2) The diffusivity in the annealed Cu did not depend on the cathodic current densities in the range of ic=2.5 to 250 A·m−2, i.e., the hydrogen concentration in the cathodic surface, but in the case of as-cold-rolled Cu, it was slightly low, when the hydrogen was introduced at low ic values. While the solubility of hydrogen beneath the cathodic surface for each specimen increased with an increase of ic value, the difference of solubility between the annealed Cu specimen and the as-cold-rolled one was not remarkable at 315±1 K.(3) The temperature dependences of the diffusivity (D) and solubility (C) of hydrogen in the annealed Cu determined at the temperature range of 292 to 339 K under ic=10 A·m−2 can be described as follows:(This article is not displayable. Please see full text pdf.) {\textbackslash} +oindentOn the other hand, compared with annealed Cu, the as-cold-rolled Cu had a lower diffusivity and slightly higher activation energy for diffusion, and the hydrogen absorption occurred by the exothermic reaction.}, + number = {3}, + journal = {Journal of the Japan Institute of Metals}, + author = {Sakamoto, Yoshiichi and Takao, Keizo}, + year = {1982}, + keywords = {Experiment, Copper}, + pages = {285--290}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\QG77JNDI\\Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:application/pdf;J-Stage - Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CCJFTBT6\\en.html:text/html;Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:D\:\\Logiciels\\data_zotero\\storage\\7YM46RCF\\Sakamoto et Takao - 1982 - The Electrochemical Determination of Diffusivity a.pdf:application/pdf}, } -@book{young_high_2016, - title = {High {Temperature} {Oxidation} and {Corrosion} of {Metals}}, - isbn = {978-0-08-100119-6}, - abstract = {High Temperature Oxidation and Corrosion of Metals, Second Edition, provides a high level understanding of the fundamental mechanisms of high temperature alloy oxidation. It uses this understanding to develop methods of predicting oxidation rates and the way they change with temperature, gas chemistry, and alloy composition. The book focuses on the design and selection of alloy compositions which provide optimal resistance to attack by corrosive gases, providing a rigorous treatment of the thermodynamics and kinetics underlying high temperature alloy corrosion. In addition, it emphasizes quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities, and alloy compositions. Users will find this book to be an indispensable source of information for researchers and students who are dealing with high temperature corrosion.Emphasizes quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities, and alloy compositionsUses phase diagrams and diffusion paths to analyze and interpret scale structures and internal precipitation distributionsPresents a detailed examination of corrosion in industrial gases (water vapor effects, carburization and metal dusting, sulphidation)Contains numerous micrographs, phase diagrams, and tabulations of relevant thermodynamic and kinetic data Combines physical chemistry and materials science methodologiesProvides two completely new chapters (chapters 11 and 13), and numerous other updates throughout the text}, +@article{ishikawa_diffusivity_1985, + title = {The diffusivity of hydrogen in copper at low temperatures}, + volume = {46}, + issn = {00223697}, + url = {https://linkinghub.elsevier.com/retrieve/pii/0022369785901106}, + doi = {10.1016/0022-3697(85)90110-6}, + abstract = {An electrochemical method has been used to measure the diffusivity of hydrogen in copper in the temperature range 299-322.5 K. Both uncoated and Pd-coated copper foils were used. The measurements show, in combination with other data, that there are no deviations from classical Arrhenius diffusion behavior in the entire temperature range from 1200 down to 300 K.}, language = {en}, - publisher = {Elsevier}, - author = {Young, David John}, - month = may, - year = {2016}, - note = {Google-Books-ID: TVXBBwAAQBAJ}, - keywords = {Science / Chemistry / Physical \& Theoretical, Technology \& Engineering / Materials Science / General, Technology \& Engineering / Metallurgy}, + number = {4}, + urldate = {2019-11-22}, + journal = {Journal of Physics and Chemistry of Solids}, + author = {Ishikawa, Thomaz and McLellan, Rex B.}, + month = jan, + year = {1985}, + keywords = {Experiment, Copper}, + pages = {445--447}, + file = {Ishikawa et McLellan - 1985 - The diffusivity of hydrogen in copper at low tempe.pdf:D\:\\Logiciels\\data_zotero\\storage\\GAHNP7UP\\Ishikawa et McLellan - 1985 - The diffusivity of hydrogen in copper at low tempe.pdf:application/pdf}, } -@techreport{devan_corrosion_1962, - title = {{CORROSION} {BEHAVIOR} {OF} {REACTOR} {MATERIALS} {IN} {FLUORIDE} {SALT} {MIXTURES}}, - url = {https://www.osti.gov/biblio/4774669}, - abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information}, - language = {English}, - number = {ORNL-TM-328}, - urldate = {2021-04-16}, - institution = {Oak Ridge National Lab., Tenn.}, - author = {DeVan, J. H. and Evans, I. I. I.}, - month = sep, - year = {1962}, - doi = {10.2172/4774669}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ATGWQ2H8\\4774669.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4XUW6QLP\\DeVan et Evans - 1962 - CORROSION BEHAVIOR OF REACTOR MATERIALS IN FLUORID.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PZHJDYGL\\4774669.html:text/html}, +@article{nagai_hydrogen_1996, + title = {Hydrogen desorption from copper during ion bombardment measured by {SIMS}}, + volume = {47}, + issn = {0042207X}, + url = {https://linkinghub.elsevier.com/retrieve/pii/0042207X96001479}, + doi = {10.1016/0042-207X(96)00147-9}, + abstract = {Secondary ion mass spectrometry (SIMS) is a sensitive analysis method for hydrogen. In this paper, SIMS is used to observe the hydrogen desorption from copper caused by an ion bombardment, and the measurements reveal the following: hydrogen ion intensity is reduced by the industrial manufacturing procedure of copper, i.e. intermediate annealing and cold working. The less porosities the copper includes, the less hydrogen desorption it shows even though the hydrogen concentration of copper bulk is the same. The former suggests that hydrogen desorption from copper is promoted by thermal diffusion and grain boundary diffusion, and the latter suggests that the hydrogen desorption phenomena is closely related to the microstructural defects like grain boundaries or porosities that enhance the diffusion of hydrogen. Copyright 0 1996 Elsevier Science Ltd.}, + language = {en}, + number = {6-8}, + urldate = {2019-11-22}, + journal = {Vacuum}, + author = {Nagai, Y and Saito, Y and Matuda, N}, + month = jun, + year = {1996}, + keywords = {Experiment, Copper}, + pages = {737--739}, + file = {Nagai et al. - 1996 - Hydrogen desorption from copper during ion bombard.pdf:D\:\\Logiciels\\data_zotero\\storage\\NT4759FQ\\Nagai et al. - 1996 - Hydrogen desorption from copper during ion bombard.pdf:application/pdf}, } -@article{zheng_corrosion-induced_2016, - title = {Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten {Li2BeF4}({FLiBe}) salt}, - volume = {482}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311516309138}, - doi = {10.1016/j.jnucmat.2016.10.023}, - abstract = {The microstructural developments in the near-surface regions of AISI 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) salt have been investigated with the goal of using this material for the construction of the fluoride salt-cooled high-temperature reactor (FHR), a leading nuclear reactor concept for the next generation nuclear plants (NGNP). Tests were conducted in molten FLiBe salt (melting point: 459 °C) at 700 °C in graphite crucibles and 316 stainless steel crucibles for exposure duration of up to 3000 h. Corrosion-induced microstructural changes in the near-surface regions of the samples were characterized using scanning electron microscopy (SEM) in conjunction with energy dispersive x-ray spectroscopy (EDS) and electron backscatter diffraction (EBSD), and scanning transmission electron microscopy (STEM) with EDS capabilities. Intergranular corrosion attack in the near-surface regions was observed with associated Cr depletion along the grain boundaries. High-angle grain boundaries (15–180°) were particularly prone to intergranular attack and Cr depletion. The depth of attack extended to the depths of 22 μm after 3000-h exposure for the samples tested in graphite crucible, while similar exposure in 316 stainless steel crucible led to the attack depths of only about 11 μm. Testing in graphite crucibles led to the formation of nanometer-scale Mo2C, Cr7C3 and Al4C3 particle phases in the near-surface regions of the material. The copious depletion of Cr in the near-surface regions induced a γ-martensite to α-ferrite phase (FeNix) transformation. Based on the microstructural analysis, a thermal diffusion controlled corrosion model was developed and experimentally validated for predicting long-term corrosion attack depth.}, - language = {en}, - urldate = {2021-04-16}, - journal = {Journal of Nuclear Materials}, - author = {Zheng, Guiqiu and He, Lingfeng and Carpenter, David and Sridharan, Kumar}, - month = dec, - year = {2016}, - keywords = {Microstructure, Corrosion, Molten salt, 316 stainless steel, Nuclear reactor}, - pages = {147--155}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GH3UXQSJ\\Zheng et al. - 2016 - Corrosion-induced microstructural developments in .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8KAF5DBG\\S0022311516309138.html:text/html}, +@article{elliott_absorption_1995, + title = {Absorption of hydrogen in copper}, + volume = {91}, + issn = {1364-5455}, + url = {https://pubs.rsc.org/en/content/articlelanding/1995/ft/ft9959103659}, + doi = {10.1039/FT9959103659}, + abstract = {Reduction of an alumina-supported copper catalyst under the conditions used as standard for the reduction of the Cu/ZnO/Al2O3 methanol-synthesis catalysts produces multilayers of hydrogen in the copper. This absorption of the hydrogen results in a reconstruction of the copper with the effect that only the surface hydrogen may be thermally desorbed. Thermal desorption of the surface hydrogen allows the surface copper atoms to migrate to a new structure, possibly their original structure, which prohibits thermally induced evolution of the subsurface hydrogen. Reduction of surface oxidised copper containing subsurface hydrogen by CO (0.1 bar, 473 K) results in the explosive evolution of subsurface hydrogen.}, + language = {en}, + number = {20}, + urldate = {2019-11-21}, + journal = {Journal of the Chemical Society, Faraday Transactions}, + author = {Elliott, A. J. and Sakakini, B. and Tabatabaei, J. and Waugh, K. C. and Zemicael, F. W. and Hadden, R. A.}, + month = jan, + year = {1995}, + keywords = {Copper}, + pages = {3659--3662}, + file = {Elliott et al. - 1995 - Absorption of hydrogen in copper.pdf:D\:\\Logiciels\\data_zotero\\storage\\QXCFFQKB\\Elliott et al. - 1995 - Absorption of hydrogen in copper.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ICR9VILL\\ft9959103659.html:text/html}, } -@article{olson_materials_2009, - series = {Fluorine \& {Nuclear} {Energy}}, - title = {Materials corrosion in molten {LiF}–{NaF}–{KF} salt}, - volume = {130}, - issn = {0022-1139}, - url = {https://www.sciencedirect.com/science/article/pii/S002211390800119X}, - doi = {10.1016/j.jfluchem.2008.05.008}, - abstract = {Corrosion tests of high temperature alloys, Hastelloy-N, Hastelloy-X, Haynes-230, Inconel-617, and Incoloy-800H were performed in molten fluoride salt, FLiNaK (LiF–NaF–KF:46.5–11.5–42mol\%) with the goal of understanding the corrosion mechanisms and ranking these alloys for their suitability for molten fluoride salt heat exchanger and thermal storage applications. The tests were performed at 850°C for 500h in sealed graphite crucibles under an argon cover gas. Corrosion was noted to occur predominantly by dealloying of Cr from the alloys, an effect that was particularly pronounced at the grain boundaries of these alloys. Weight-loss due to corrosion generally correlated with the initial Cr-content of the alloys, and was consistent with the Cr-content measured in the salts after corrosion tests. Two Cr-free alloys, Ni-201 and Nb–1Zr, were also tested. Ni-201, a nearly pure Ni alloy with minor alloying additions, exhibited good resistance to corrosion, whereas Nb–1Zr alloy exhibited extensive corrosion attack. The graphite crucible may have accelerated the corrosion process by promoting the formation of carbide phases on the walls of the test crucibles, but did not alter the basic corrosion mechanism.}, +@article{yasumori_mechanism_1974, + title = {Mechanism of {Hydrogen} {Adsorption} and {Hydrogen}-{Deuterium} {Equilibration} on {Copper} {Surface}}, + volume = {13}, + issn = {1347-4065}, + url = {https://iopscience.iop.org/article/10.7567/JJAPS.2S2.485/meta}, + doi = {10.7567/JJAPS.2S2.485}, language = {en}, - number = {1}, - urldate = {2021-04-16}, - journal = {Journal of Fluorine Chemistry}, - author = {Olson, Luke C. and Ambrosek, James W. and Sridharan, Kumar and Anderson, Mark H. and Allen, Todd R.}, + number = {S2}, + urldate = {2019-11-21}, + journal = {Japanese Journal of Applied Physics}, + author = {Yasumori, Iwao and Momma, Naohiro and Kiyomiya, Makoto}, month = jan, - year = {2009}, - keywords = {Corrosion, Molten salt, Materials, FLiNaK, Fluorides}, - pages = {67--73}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QFJPC5YY\\Olson et al. - 2009 - Materials corrosion in molten LiF–NaF–KF salt.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H243BZZA\\S002211390800119X.html:text/html}, + year = {1974}, + keywords = {Copper}, + pages = {485}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\W6APLSH6\\Yasumori et al. - 1974 - Mechanism of Hydrogen Adsorption and Hydrogen-Deut.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\8KTWBQP8\\JJAPS.2S2.html:text/html}, } -@article{raiman_facility_2014, - title = {A facility for studying irradiation accelerated corrosion in high temperature water}, - volume = {451}, +@article{de_temmerman_effect_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Effect of high-flux {H}/{He} plasma exposure on tungsten damage due to transient heat loads}, + volume = {463}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311514001317}, - doi = {10.1016/j.jnucmat.2014.03.022}, - abstract = {A facility for the study of irradiation accelerated corrosion in high temperature water using in situ proton irradiation has been developed and validated. A specially designed beamline and flowing-water corrosion cell added to the 1.7MV tandem accelerator at the Michigan Ion Beam Laboratory provide the capability to study the simultaneous effects of displacement damage and radiolysis on corrosion. A thin sample serves as both a “window” into the corrosion cell through which the proton beam passes completely, and the sample for assessing irradiation accelerated corrosion. The facility was tested by irradiating stainless steel samples at beam current densities between 0.5 and 10μA/cm2 in 130°C and 320°C deaerated water, and 320°C water with 3wppm H2. Increases in the conductivity and dissolved oxygen content of the water varied with the proton beam current, suggesting that proton irradiation was accelerating the corrosion of the sample. Conductivity increases were greatest at 320°C, while DO increases were highest at 130°C. The addition of 3wppm H2 suppressed DO below detectable levels. The facility will enable future studies into the effect of irradiation on corrosion in high temperature water with in situ proton irradiation.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514006758}, + doi = {10.1016/j.jnucmat.2014.09.075}, + abstract = {The thermal shock behaviour of tungsten exposed to high-flux plasma is studied using a high-power laser. The cases of laser-only, sequential laser and hydrogen (H) plasma and simultaneous laser plus H plasma exposure are studied. H plasma exposure leads to an embrittlement of the material and the appearance of a crack network originating from the centre of the laser spot. Under simultaneous loading, significant surface melting is observed. In general, H plasma exposure lowers the heat flux parameter (FHF) for the onset of surface melting by ∼25\%. In the case of He-modified (fuzzy) surfaces, strong surface deformations are observed already after 1000 laser pulses at moderate FHF=19MJm−2s−1/2, and a dense network of fine cracks is observed. These results indicate that high-fluence ITER-like plasma exposure influences the thermal shock properties of tungsten, lowering the permissible transient energy density beyond which macroscopic surface modifications begin to occur.}, language = {en}, - number = {1}, - urldate = {2021-04-17}, + urldate = {2019-11-21}, journal = {Journal of Nuclear Materials}, - author = {Raiman, Stephen S. and Flick, Alexander and Toader, Ovidiu and Wang, Peng and Samad, Nassim A. and Jiao, Zhijie and Was, Gary S.}, + author = {De Temmerman, G. and Morgan, T. W. and van Eden, G. G. and de Kruif, T. and Wirtz, M. and Matejicek, J. and Chraska, T. and Pitts, R. A. and Wright, G. M.}, month = aug, - year = {2014}, - pages = {40--47}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\963I7BH7\\S0022311514001317.html:text/html}, + year = {2015}, + keywords = {Experiment, Fuzz}, + pages = {198--201}, + file = {De Temmerman et al. - 2015 - Effect of high-flux HHe plasma exposure on tungst.pdf:D\:\\Logiciels\\data_zotero\\storage\\CAPGFGZT\\De Temmerman et al. - 2015 - Effect of high-flux HHe plasma exposure on tungst.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZT9DUUYP\\S0022311514006758.html:text/html}, } -@article{reza_thermal_2020, - title = {Thermal diffusivity degradation and point defect density in self-ion implanted tungsten}, - volume = {193}, - issn = {1359-6454}, - url = {https://www.sciencedirect.com/science/article/pii/S1359645420302214}, - doi = {10.1016/j.actamat.2020.03.034}, - abstract = {Using transient grating spectroscopy (TGS) we measure the thermal diffusivity of tungsten exposed to different levels of 20 MeV self-ion irradiation. Damage as low as 3.2 × 10−4 displacements per atom (dpa) causes a measurable reduction in thermal diffusivity. Doses of 0.1 dpa and above, up to 10 dpa, give a degradation of ∼55\% from the pristine value at room temperature. Using a kinetic theory model, the density of irradiation-induced point defects is estimated based on the measured changes in thermal diffusivity as a function of dose. These predictions are compared with point defect and dislocation loop densities observed in transmission electron microscopy (TEM). Molecular dynamics (MD) predictions are combined with the TEM observations to estimate the density of point defects associated with defect clusters too small to be probed by TEM. When these “invisible” defects are accounted for, the total point defect density agrees well with that estimated from TGS for a range of doses spanning 3 orders of magnitude. Kinetic theory modelling is also used to estimate the thermal diffusivity degradation expected due to TEM-visible and invisible defects. Finely distributed invisible defects appear to play a much more important role in the thermal diffusivity reduction than larger TEM-visible dislocation loops. This work demonstrates the capability of TGS, in conjunction with kinetic theory models, to provide rapid, quantitative insight into defect densities and property evolution in irradiated materials.}, +@article{skinner_recent_2008, + title = {Recent advances on hydrogen retention in {ITER}'s plasma-facing materials: beryllium, carbon, and tunsgten}, + volume = {54}, + abstract = {Management of tritium inventory remains one of the grand challenges in the development of fusion energy, and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the International Atomic Energy Agency organized a Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001–2006. This dealt with hydrogenic retention in ITER’s plasma-facing materials—Be, C, and W—and in compounds (mixed materials) of these elements as well as tritium removal techniques. The results of the CRP are summarized in this paper together with recommendations for ITER. Basic parameters of diffusivity, solubility, and trapping in Be, C, and W are reviewed. For Be, the development of open porosity can account for transient hydrogenic pumping, but long-term retention will be dominated by codeposition. Codeposition is also the dominant retention mechanism for carbon and remains a serious concern for both Be- and C-containing layers. Hydrogenic trapping in unirradiated tungsten is low but will increase with ion and neutron damage. Mixed materials will be formed in a tokamak, and these can also retain significant amounts of hydrogen isotopes. Oxidative and photonbased techniques for detritiation of plasma-facing components are described.}, language = {en}, - urldate = {2021-04-19}, - journal = {Acta Materialia}, - author = {Reza, Abdallah and Yu, Hongbing and Mizohata, Kenichiro and Hofmann, Felix}, - month = jul, - year = {2020}, - keywords = {Fusion materials, Point defects, Thermal conductivity, Transient grating spectroscopy}, - pages = {270--279}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z94RE44L\\S1359645420302214.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EHQ8FRQ3\\Reza et al. - 2020 - Thermal diffusivity degradation and point defect d.pdf:application/pdf}, + author = {Skinner, C H and Haasz, A A and Alimov, V Kh and Bekris, N and Causey, R A and Clark, R E H and Coad, J P and Davis, J W and Doerner, R P and Mayer, M and Pisarev, A and Roth, J and Tanabe, T}, + year = {2008}, + pages = {55}, + file = {Skinner et al. - 2008 - Recent advances on hydrogen retention in ITER's pl.pdf:D\:\\Logiciels\\data_zotero\\storage\\BLIUUNI4\\Skinner et al. - 2008 - Recent advances on hydrogen retention in ITER's pl.pdf:application/pdf}, } -@article{siccinio_feasibility_2021, - title = {Feasibility of {D}-{D} start-up under realistic technological assumptions for {EU}-{DEMO}}, - volume = {171}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621003306}, - doi = {10.1016/j.fusengdes.2021.112554}, - abstract = {One of the main issues in view of the realization of a DEMOnstration fusion reactor is the availability of a sufficient external supply of tritium (T) to start operation. T is an unstable nuclide, which is almost absent in nature and is currently available as by-product in e.g. CANDU, whose operation in the next decades (both in terms of life extension of existing reactors and construction of new ones) is at the moment under debate. During DEMO operation, T will be generated on-site by breeding blanket, employing the neutrons originating from D-T reaction. However, it is considered that a certain initial amount of T is needed to start operation, the so-called start-up inventory. An alternative approach consists of obtaining the start-up inventory exploiting reactions occurring in a D-D plasma, which generate T both directly in the plasma and via breeding in the breeding blanket. In the present paper, the conditions under which D-D start-up becomes a favorable option for a power plant are discussed. The analysis mainly focuses on the EU-DEMO reactor concept, for which design data are sufficient for a fairly quantitative evaluation of the relevant parameters. It is found that the unavoidable presence of elements requiring saturation before they are able to release significant amounts of T clamps the T production rate to the same order of magnitude as D-D reaction rate. Thus, under very optimistic assumptions, several hundreds of full-current D-D discharges are necessary for T to be available for plasma fueling, but more realistic estimates let this number raise up to several thousands.}, +@article{becquart_density_2009, + series = {Fusion {Reactor} {Materials}}, + title = {A density functional theory assessment of the clustering behaviour of {He} and {H} in tungsten}, + volume = {386-388}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311508008179}, + doi = {10.1016/j.jnucmat.2008.12.085}, + abstract = {We have used density functional theory based ab initio calculations to investigate the tendency of He and H to form clusters. For both species the most stable interstitial configuration is in a tetrahedral site, however their clustering tendencies are totally different. The He–He interaction is purely elastic in nature and as such highly binding at close separation distances. The H–H interaction on the other hand is almost negligible since the elastic binding effect is compensated for by the change in effective position of the H states in the density of states. He atoms always bond more strongly to HexHy complexes in a vacancy than H atoms.}, language = {en}, - urldate = {2021-04-19}, - journal = {Fusion Engineering and Design}, - author = {Siccinio, M. and Chiovaro, P. and Cismondi, F. and Coleman, M. and Day, C. and Fable, E. and Federici, G. and Härtl, T. and Schwenzer, J. and Spagnuolo, G. A.}, - month = oct, - year = {2021}, - keywords = {Tritium, DD-start-up, EU-DEMO, Fuel cycle}, - pages = {112554}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EKUZB92B\\Siccinio et al. - 2021 - Feasibility of D-D start-up under realistic techno.pdf:application/pdf}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Becquart, Charlotte S. and Domain, Christophe}, + month = apr, + year = {2009}, + keywords = {Density Functional Theory}, + pages = {109--111}, + file = {Becquart et Domain - 2009 - A density functional theory assessment of the clus.pdf:D\:\\Logiciels\\data_zotero\\storage\\YUEFIHCN\\Becquart et Domain - 2009 - A density functional theory assessment of the clus.pdf:application/pdf}, } -@article{wang_effect_2021, - title = {Effect of helium pre-implantation on the thermal shock performance of tungsten}, - volume = {27}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121000272}, - doi = {10.1016/j.nme.2021.100934}, - abstract = {In ITER and future tokamaks, high heat flux loads will lead to recrystallization and decrease in toughness and thermal shock resistance of tungsten plasma facing materials, resulting in crack network formation and possible failure. In this study, thermal shock tests of blank, helium-plasma-exposed and helium-ion-irradiated rolled tungsten with/without isothermal annealing are conducted. Without annealing, cracks start to form in blank tungsten at the power density of 0.35 GW/m2, while no cracks are observed on the loaded surface of helium-plasma-exposed and helium-ion-irradiated ones. After annealing at 1473 K for 1 h, the recrystallization fractions of the three kinds of tungsten are around 50\%, 18\% and 8\%, respectively. The following thermal shock tests of the annealed samples show that the cracking thresholds of blank and helium-plasma-exposed ones reduce to 0.3 GW/m2, while cracks do not appear in the helium-ion-irradiated one at this power density. Surface roughening thresholds are also improved in helium pre-implanted samples and do not change after annealing. It indicates that both helium plasma and ion irradiation improve the thermal stability and damaging threshold of tungsten, and helium ion irradiation has a stronger influence. This suggests a potential benefit of helium to extend the service lifetime of tungsten.}, +@phdthesis{hodille_study_2016, + title = {Study and modeling of the deuterium trapping in {ITER} relevant materials}, + url = {https://tel.archives-ouvertes.fr/tel-01477426}, + abstract = {During ITER operation, important flux of Hydrogen Isotopes (HIs) constituting the fuel interact with the plasma facing components (PFC) of the machine. In the case of tungsten (W) making the divertor which is the most exposed area to the plasma wall interaction, the incident flux can be implanted and diffuse inside the bulk material inducing a trapping of the fuel. To safety issue, the tritium inventory retained in ITER’s PFC is limited. In addition, the outgassing of the fuel during plasma operation can impact the edge plasma control. The aim of this PhD project is first to determined relevant trapping parameters of the fuel in W (detrapping energies/temperatures and trap concentrations) by modelling experimental results. The simulations of experimental results shows that under specific condition, the HI implantation can induce the formation of mono-vacancies containing impurities. In addition to this induced trap, 2 intrinsic traps are present in W. This 3 traps retain HIs up to 700 K. Finally, it has been shown that the damaged W by heavy ions or neutrons contains dislocations, dislocation loops and cavities that can trap HIs up to 1000 K. After determining the fuel retention properties of W, the HIs retention during ITER operation is estimated. During this operation, the PFC temperature reaches around 1000 K so the simulations show that the damaged W retains much more HIs than the undamaged W.}, language = {en}, - urldate = {2021-04-22}, - journal = {Nuclear Materials and Energy}, - author = {Wang, Yingdi and Guo, Wangguo and Zhu, Yida and Yuan, Yue and Peng, Jiaguan and Ren, Mengchong and Wang, Zheng and Cheng, Long and Chen, Zhe and Lian, Youyun and Liu, Xiang and Lu, Guang-Hong}, - month = jun, - year = {2021}, - keywords = {Helium, Recrystallization retarding, Surface cracking, Surface roughening, Thermal shocks}, - pages = {100934}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DHD3XS3T\\S2352179121000272.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5W7KSTVY\\Wang et al. - 2021 - Effect of helium pre-implantation on the thermal s.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9KXAR29U\\S2352179121000272.html:text/html}, + urldate = {2019-10-07}, + school = {Aix-Marseille}, + author = {Hodille, Etienne}, + month = nov, + year = {2016}, + keywords = {Macroscopic rate equations}, + file = {Hodille - 2016 - Study and modeling of the deuterium trapping in IT.pdf:D\:\\Logiciels\\data_zotero\\storage\\Q2U7IN23\\Hodille - 2016 - Study and modeling of the deuterium trapping in IT.pdf:application/pdf}, } -@article{parish_grain_2017, - title = {Grain orientations and grain boundaries in tungsten nonotendril fuzz grown under divertor-like conditions}, - volume = {127}, - issn = {1359-6462}, - url = {https://www.sciencedirect.com/science/article/pii/S1359646216304468}, - doi = {10.1016/j.scriptamat.2016.09.018}, - abstract = {We grew nanotendril “fuzz” on tungsten via plasma exposure and performed transmission Kikuchi diffraction (tKD) in scanning electron microscopy of isolated nanotendrils. 900°C, 1023He/m2sec, 4×1026He/m2 exposure of tungsten produced a deep and fully developed nanotendril mat. tKD of isolated nanotendrils indicated that there was no preferred crystallographic direction oriented along the long axes of the tendrils, and the grain boundary character showed slightly preferential orientations. Tendril growth is sufficiently non-equilibrium to prevent any preference of growth direction to manifest measurably, and that new high-angle boundaries (with new grains and grain-growth axes) nucleate randomly along the tendrils during growth.}, - language = {en}, - urldate = {2021-04-20}, - journal = {Scripta Materialia}, - author = {Parish, Chad M. and Wang, Kun and Doerner, Russel P. and Baldwin, Matthew J.}, - month = jan, - year = {2017}, - keywords = {Tungsten, Fusion, Fusion energy, Plasma simulation, Transmission Kikuchi diffraction}, - pages = {132--135}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MGF7RBXX\\S1359646216304468.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DVFSAUKK\\Parish et al. - 2017 - Grain orientations and grain boundaries in tungste.pdf:application/pdf}, +@article{ning_improved_2012, + title = {An {Improved} {Cluster} {Dynamics} {Model} {For} {Hydrogen} {Retention} {In} {Tungsten}}, + url = {https://www.semanticscholar.org/paper/An-Improved-Cluster-Dynamics-Model-For-Hydrogen-In-Ning-Li/75873a7dd89cabc7474c953e267bb93105c3e705}, + doi = {10.1142/S0129183112500428}, + abstract = {An improved cluster dynamics model has been developed for studying the behaviors of hydrogen retention in tungsten under hydrogen ions irradiation. In addition to different types of objects, adopting up-to-date parameters and complex reaction processes, we newly introduce ion-induced and natural defects into our model. This improved model programmed in IRadMat2 could describe very well the depth distributions and the amounts of hydrogen retained in tungsten under different radiation conditions. The calculated results agree with the experimental ones much better than the previous model, especially for the depth-distribution of D retained in W, which imply that this model is applicable to the evolution of defects especially for low energy high flux ions irradiated on plasma-facing materials.}, + journal = {International Journal of Modern Physics C}, + author = {Ning, Ruola and Li, Yon Gan and Zhou, Weihong and Zeng, Zhi and Ju, Xin}, + year = {2012}, + keywords = {Cluster dynamics}, + file = {Ning et al. - 2012 - An Improved Cluster Dynamics Model For Hydrogen Re.pdf:D\:\\Logiciels\\data_zotero\\storage\\DUALYV4S\\Ning et al. - 2012 - An Improved Cluster Dynamics Model For Hydrogen Re.pdf:application/pdf}, } -@article{alimov_surface_2009, - title = {Surface morphology and deuterium retention in tungsten exposed to low-energy, high flux pure and helium-seeded deuterium plasmas}, - volume = {T138}, - issn = {0031-8949, 1402-4896}, - url = {https://iopscience.iop.org/article/10.1088/0031-8949/2009/T138/014048}, - doi = {10.1088/0031-8949/2009/T138/014048}, - abstract = {Blistering and deuterium retention in re-crystallized tungsten exposed to low-energy, high flux pure and helium-seeded D plasmas to a fluence of 1027 D m−2 have been examined with scanning electron microscopy, thermal desorption spectroscopy, and the D(3He, p)4He nuclear reaction at 3He energies varied from 0.69 to 4.0 MeV. In the case of exposure to pure D plasma (38 eV D−1), blisters with various shapes and sizes depending on the exposure temperature are found on the W surface. No blisters appear at temperatures above 700 K. The deuterium retention increases with the exposure temperature, reaching a maximum value of about 1022 D m−2 at 480 K, and then decreases as the temperature rises further. Seeding of 76 eV He ions into the D plasma significantly reduces the D retention at elevated temperatures and prevents formation of the blisters.}, +@phdthesis{muthali_electronic_2019, + title = {Electronic structure calculations and thermodynamic models for energy-producing systems}, language = {en}, - urldate = {2021-04-20}, - journal = {Physica Scripta}, - author = {Alimov, V Kh and Shu, W M and Roth, J and Sugiyama, K and Lindig, S and Balden, M and Isobe, K and Yamanishi, T}, - month = dec, - year = {2009}, - pages = {014048}, - file = {Alimov et al. - 2009 - Surface morphology and deuterium retention in tung.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IA48UPDI\\Alimov et al. - 2009 - Surface morphology and deuterium retention in tung.pdf:application/pdf}, -} - -@misc{noauthor_effect_nodate, - title = {Effect of the presence of helium in tungsten on deuterium retention - {ScienceDirect}}, - url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/science/article/pii/S0022311521000969?via%3Dihub}, - urldate = {2021-04-20}, - file = {Effect of the presence of helium in tungsten on deuterium retention - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6JQILEBL\\S0022311521000969.html:text/html}, + school = {Aix-Marseille}, + author = {Muthali, Ajmalghan}, + month = sep, + year = {2019}, + keywords = {Density Functional Theory}, + file = {Muthali - Electronic structure calculations and thermodynami.pdf:D\:\\Logiciels\\data_zotero\\storage\\SWIUSS7F\\Muthali - Electronic structure calculations and thermodynami.pdf:application/pdf}, } -@article{calderoni_measurement_2008, - title = {Measurement of tritium permeation in flibe ({2LiF}–{BeF2})}, - volume = {83}, - issn = {09203796}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379608000926}, - doi = {10.1016/j.fusengdes.2008.05.016}, - abstract = {This paper reports on the experimental investigation of tritium permeation in flibe (2LiF-BeF2) at the Safety and Tritium Applied Research facility of the Idaho National Laboratory. A stainless steel cell formed by two independent volumes separated by a 2mm thick nickel membrane is maintained at temperatures between 500 and 700 degrees Celsius. A controlled amount of T2 gas is flown in excess of argon in the source volume in contact with the bottom side of the nickel membrane, while a layer of molten salt is in contact with the top side. The tritium permeating above the liquid surface is carried by an argon flow to a diagnostic system comprised of a quadrupole mass spectrometer, a gas chromatographer and a proportional counter. Tritium permeability in flibe as a function of temperature is determined by the measured permeation flow rates reached in steady-state conditions, while the diffusivity is determined by fitting the transient process with the analytical solution for the diffusion process. As a result, the solubility of tritium in flibe as a function of temperature is also determined.}, +@article{hammond_helium_2017, + title = {Helium, hydrogen, and fuzz in plasma-facing materials}, + volume = {4}, + issn = {2053-1591}, + doi = {10.1088/2053-1591/aa8c22}, + abstract = {Tungsten, the primary material under consideration as the divertor material in magnetic-confinement nuclear fusion reactors, has been known for the last decade to form ‘fuzz’—a layer of microscopic, high-void-fraction features on the surface—after only a few hours of exposure to helium plasma. Fuzz has also been observed in molybdenum, tantalum, and several other metals. Helium bubbles in tungsten and other metals are also known to change the hardness of the surface, accumulate at grain boundaries and dislocations, and increase hydrogen isotope retention. This article reviews helium- and hydrogen-induced surface evolution, including fuzz formation, in tungsten and other plasma-facing materials, as well as modeling and experimental efforts that have been undertaken to understand the mechanisms of fuzz formation, helium and hydrogen transport in plasma-facing materials, and relevant atomic-scale and electronic effects relevant to plasma-facing materials.}, language = {en}, - number = {7-9}, - urldate = {2021-05-05}, - journal = {Fusion Engineering and Design}, - author = {Calderoni, P. and Sharpe, P. and Hara, M. and Oya, Y.}, - month = dec, - year = {2008}, - keywords = {Tritium, Diffusivity, Solubility, Fusion, Molten salt}, - pages = {1331--1334}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LYH674HW\\S0920379608000926.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SN5FMKAY\\Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:application/pdf;Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Q8GBT577\\Calderoni et al. - 2008 - Measurement of tritium permeation in flibe (2LiF–B.pdf:application/pdf}, + number = {10}, + urldate = {2019-10-25}, + journal = {Materials Research Express}, + author = {Hammond, Karl D.}, + month = oct, + year = {2017}, + keywords = {Experiment, Bubble, Fuzz}, + pages = {104002}, + file = {Hammond - 2017 - Helium, hydrogen, and fuzz in plasma-facing materi.pdf:D\:\\Logiciels\\data_zotero\\storage\\EEYZCISS\\Hammond - 2017 - Helium, hydrogen, and fuzz in plasma-facing materi.pdf:application/pdf}, } -@article{niu_effect_2021, - title = {Effect of temperature on the growth and surface bursting of {He} nano-bubbles in {W} under fusion-relevant {He} ion irradiations}, - volume = {163}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379620307079}, - doi = {10.1016/j.fusengdes.2020.112159}, - abstract = {Under fusion-relevant He+ irradiations, the W surface temperature is one of the most important parameters for controlling the fuzz growth over the W divertor targets, which is associated with the surface bursting of He nano-bubbles. Using He reaction rate model in W, we investigate the effect of temperature on the growth and surface bursting of He nano-bubbles under low-energy (100 eV) and large-flux (∼1022/m2⋅s) He+ irradiations. Increasing the irradiation temperature from 750 to 2500 K leads to a significant change in both the radius of He nano-bubbles and He retention. At an elevated temperature, He solute atoms prefer to rapidly diffuse into He nano-bubbles, thus affecting their concentration, growth and surface bursting. The decrease in He retention is attributed to an increase in the hop rate of solute He atoms in the W top layer, resulting in the significant He release from the W surface. The radius and density of He nano-bubbles calculated by our model are consistent with our experimental observation.}, +@article{bernard_temperature_2017, + title = {Temperature impact on the micro structure of tungsten exposed to {He} irradiation in {LHD}}, + volume = {484}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311516306560}, + doi = {10.1016/j.jnucmat.2016.10.040}, + abstract = {A new temperature controlled material probe was designed for the exposure of tungsten samples to helium plasma in the LHD. Samples were exposed to estimated fluences of ∼1023 m−2 and temperatures ranging from 65 to 600 °C. Transmission Electron Microscopy analysis allowed the study of the impact of He irradiation under high temperatures on tungsten micro structure for the first time in real-plasma exposure conditions. Both dislocation loops and bubbles appeared from low to medium temperatures and saw an impressive increase of size (factor 4 to 6) most probably by coalescence as the temperature reaches 600 °C, with 500 °C appearing as a threshold for bubble growth. Annealing of the samples up to 800 C highlighted the stability of the dislocation damages formed by helium irradiation at high surface temperature, as bubbles and dislocation loops seem to conserve their characteristics. Additional studies on cross-sections showed that bubbles were formed much deeper (70–100 nm) than the heavily damaged surface layer (10–20 nm), raising concern about the impact on the material mechanical properties conservation and potential additional trapping of hydrogen isotopes.}, language = {en}, - urldate = {2021-05-05}, - journal = {Fusion Engineering and Design}, - author = {Niu, Chunjie and Zhang, Yang and Cui, Yunqiu and Li, Xiaoping and Liu, Weifeng and Ni, Weiyuan and Fan, Hongyu and Lu, Na and Benstetter, Günther and Lei, Guangjiu and Liu, Dongping}, + urldate = {2019-10-29}, + journal = {Journal of Nuclear Materials}, + author = {Bernard, Elodie and Sakamoto, Ryuichi and Tokitani, Masayuki and Masuzaki, Suguru and Hayashi, Hiromi and Yamada, Hiroshi and Yoshida, Naoaki}, month = feb, - year = {2021}, - keywords = {Tungsten, Nuclear fusion, He ion irradiation, He nanobubble, Plasma facing materials}, - pages = {112159}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KPGXQ4BR\\S0920379620307079.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RR228XVL\\Niu et al. - 2021 - Effect of temperature on the growth and surface bu.pdf:application/pdf}, + year = {2017}, + keywords = {Experiment, Bubble, Fuzz}, + pages = {24--29}, + file = {Bernard et al. - 2017 - Temperature impact on the micro structure of tungs.pdf:D\:\\Logiciels\\data_zotero\\storage\\3QVHN3W5\\Bernard et al. - 2017 - Temperature impact on the micro structure of tungs.pdf:application/pdf}, } -@article{ezell_neutron_2021, - title = {Neutron irradiation of alloy {N} and {316L} stainless steel in contact with a molten chloride salt}, - volume = {53}, - issn = {1738-5733}, - url = {https://www.sciencedirect.com/science/article/pii/S1738573320308044}, - doi = {10.1016/j.net.2020.07.042}, - abstract = {Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. -Index Terms -Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.}, +@article{wirtz_influence_2016, + title = {Influence of helium induced nanostructures on the thermal shock performance of tungsten}, + volume = {9}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179115301198}, + doi = {10.1016/j.nme.2016.07.002}, + abstract = {Experiments were performed in the linear plasma device PSI-2 in order to investigate the synergistic effects of combined steady-state He-plasma and thermal shock exposure. Tungsten produced according to the ITER material specifications by Plansee SE, Austria, was loaded sequentially and simultaneously by steady-state He plasma and transient thermal loads induced by a laser beam. All tungsten samples were exposed to helium plasma for 40min at a base temperature of ca. 850°C and a flux of ca. 2.8×1022m−2s−1. Before, during and after the plasma exposure 1000 thermal shock pulses with a pulse duration of 1ms and a power density 0.76GW/m² were applied on the samples. The thermal shock exposure before and after plasma exposure was done at room temperature in order to investigate helium induced surface effects also within cracks. The obtained results show that the combination of He plasma with transient thermal shock events results in a severe modification such as reduced height or agglomeration of the sub-surface He-bubbles and of the created nanostructures, i.e. W-fuzz.}, + urldate = {2019-10-07}, + journal = {Nuclear Materials and Energy}, + author = {Wirtz, M. and Berger, M. and Huber, A. and Kreter, A. and Linke, J. and Pintsuk, G. and Rasinski, M. and Sergienko, G. and Unterberg, B.}, + month = dec, + year = {2016}, + keywords = {Experiment, Bubble, Fuzz}, + pages = {177--180}, + annote = { +This paper shows experimental results on tunsgten exposed to He plasma and transient thermal loads in PSI-2. +Loading was done both sequentially and simultaneously. +1000 thermal shock pulses were made (each shock is 1 ms and 0.76 GW.m{\textasciicircum}-2. +He bubbles are observed as well as tunsgten nano fuzz. +Strong surface alteration is induced : cracks, nano fuzz. +Appearance of these structures increases the risk of erosion and dust formation. +Cracks can disappear during thermal loads due to thermal expansion. +It is noted that the strike point of ELMs will be shifted during the operation of a reactor which corresponds to a case where the sample is first exposed to He plasma then to thermal heat loads. +The formation of He bubbles in the near surface region will have an influence on the thermal conductivity and the heat dissipation of a monoblock which could lead to overheating of the PFC. +}, + file = {Wirtz et al. - 2016 - Influence of helium induced nanostructures on the .pdf:D\:\\Logiciels\\data_zotero\\storage\\8B7FGA4D\\Wirtz et al. - 2016 - Influence of helium induced nanostructures on the .pdf:application/pdf}, +} + +@article{zenobia_formation_2009, + title = {Formation and retention of surface pores in helium-implanted nano-grain tungsten for fusion reactor first-wall materials and divertor plates}, + volume = {T138}, + issn = {1402-4896}, + url = {https://iopscience.iop.org/article/10.1088/0031-8949/2009/T138/014049}, + doi = {10.1088/0031-8949/2009/T138/014049}, + abstract = {Nano-grain W samples were implanted with 30 keV 3He ions to fluences of 1021, 1022 and 1023 He m−2, at temperatures ranging from approximately 1273 to 1423 K. One specimen was implanted with 30 keV 4He ions at 1273 K to 1024 He m−2. Scanning electron microscopy showed the onset of visible surface pore formation occurred between approximately 1021 and 1022 He+ m−2 and increased with higher implant fluences, eventually resulting in a ‘coral-like’ surface structure. Focused ion beam analysis revealed the depth of visible subsurface pores increased with higher doses, extending below the surface to a maximum value of approximately 730 nm. Using 3He(d, p)4He nuclear reaction analysis on 3He+ implanted specimens retained helium fluences were found to range from 4.0×1020 to 4.5×1021 He m−2. Each specimen sustained mass loss after implantation which was observed to increase with greater He+ dose.}, language = {en}, - number = {3}, - urldate = {2021-05-05}, - journal = {Nuclear Engineering and Technology}, - author = {Ezell, N. Dianne Bull and Raiman, Stephen S. and Kurley, J. Matt and McDuffee, Joel}, - month = mar, - year = {2021}, - keywords = {Irradiation, Corrosion, High-temperature experiment, Molten Salt Reactor}, - pages = {920--926}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WTQTNJPG\\S1738573320308044.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DJRL985G\\Ezell et al. - 2021 - Neutron irradiation of alloy N and 316L stainless .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KF3NNBDV\\S1738573320308044.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XCBP4Y5S\\Ezell et al. - 2021 - Neutron irradiation of alloy N and 316L stainless .pdf:application/pdf}, + urldate = {2019-10-30}, + journal = {Physica Scripta}, + author = {Zenobia, S. J. and Kulcinski, G. L.}, + month = dec, + year = {2009}, + keywords = {Experiment, Bubble, Fuzz}, + pages = {014049}, + file = {Zenobia et Kulcinski - 2009 - Formation and retention of surface pores in helium.pdf:D\:\\Logiciels\\data_zotero\\storage\\N8952AGP\\Zenobia et Kulcinski - 2009 - Formation and retention of surface pores in helium.pdf:application/pdf}, } -@article{pillai_first_2021, - title = {First steps toward predicting corrosion behavior of structural materials in molten salts}, - volume = {546}, +@article{baldwin_effects_2009, + series = {Proceedings of the 18th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion} {Device}}, + title = {The effects of high fluence mixed-species (deuterium, helium, beryllium) plasma interactions with tungsten}, + volume = {390-391}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311520313635}, - doi = {10.1016/j.jnucmat.2020.152755}, - abstract = {To address the need for physics-based models to predict corrosion behavior of materials in molten salts, the current work proposes potential methods to aid in selection of optimum materials for structural components in molten salt powered technologies. In the present work, the role of alloy thermodynamics and kinetics on governing corrosion rates of Ni-based alloys will be discussed combining experimental and computational methods. A few strategies are presented to quantify corrosion rates of Ni-based materials isothermally exposed in purified KCl-MgCl2 salts at 600 ∘ C-800 ∘ C. The influence of capsule material, potential corrosion products and role of alloy composition on the observed corrosion rates was discussed with coupled thermodynamic-kinetic models. Larger depths of corrosion attack were observed in alloy 230 specimens compared to other alloys under similar conditions was attributed to the much higher chemical activity of Cr in the alloy that results in a larger Cr chemical potential gradient.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311509002566}, + doi = {10.1016/j.jnucmat.2009.01.247}, + abstract = {W targets are exposed to D2−Be, He, D2−He and D2−Be−He plasmas in the linear-plasma-device PISCES-B to simulate the conditions expected at W strike-points in an ITER all W metal divertor scenario. In D2−Be and He plasmas, target temperatures in the range 1070–1320K lead to surface layers of Be–W alloy or nano-structured W morphology, respectively, but below 900K, neither types of layer are found to form. Both processes have kinetics reminiscent of diffusion. Alloying kinetics are optimal when surface Be availability is maximized through the formation of a deposited Be over-layer. Nano-structured layer growth at 1120K is most rapid for incident He ion fluxes above 7×1021m−2s−1. In D2−0.1He plasmas, a mixture relevant to divertor exhaust, small Be or C fractions can significantly reduce nano-structure growth in favor of the formation of a mixed material Be−W alloy or C layer.}, language = {en}, - urldate = {2021-05-05}, + urldate = {2019-10-30}, journal = {Journal of Nuclear Materials}, - author = {Pillai, R. and Raiman, S. S. and Pint, B. A.}, - month = apr, - year = {2021}, - keywords = {Corrosion rates, Coupled thermodynamic-kinetic modeling, Molten salts, Ni-based alloys}, - pages = {152755}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CICPY3FE\\S0022311520313635.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CE7L7CM4\\Pillai et al. - 2021 - First steps toward predicting corrosion behavior o.pdf:application/pdf}, + author = {Baldwin, M. J. and Doerner, R. P. and Nishijima, D. and Tokunaga, K. and Ueda, Y.}, + month = jun, + year = {2009}, + keywords = {Experiment, Fuzz}, + pages = {886--890}, + file = {Baldwin et al. - 2009 - The effects of high fluence mixed-species (deuteri.pdf:D\:\\Logiciels\\data_zotero\\storage\\CDDWNY24\\Baldwin et al. - 2009 - The effects of high fluence mixed-species (deuteri.pdf:application/pdf}, } -@article{de_temmerman_data_2021, - title = {Data on erosion and hydrogen fuel retention in {Beryllium} plasma-facing materials}, - volume = {27}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121000740}, - doi = {10.1016/j.nme.2021.100994}, - abstract = {ITER will use beryllium as a plasma-facing material in the main chamber, covering a total surface area of about 620 m2. Given the importance of beryllium erosion and co-deposition for tritium retention in ITER, significant efforts have been made to understand the behaviour of beryllium under fusion-relevant conditions with high particle and heat loads. This paper provides a comprehensive report on the state of knowledge of beryllium behaviour under fusion-relevant conditions: the erosion mechanisms and their consequences, beryllium migration in JET, fuel retention and dust generation. The paper reviews basic laboratory studies, advanced computer simulations and experience from laboratory plasma experiments in linear simulators of plasma–wall interactions and in controlled fusion devices using beryllium plasma-facing components. A critical assessment of analytical methods and simulation codes used in beryllium studies is given. The overall objective is to review the existing set of data with a broad literature survey and to identify gaps and research needs to broaden the database for ITER.}, +@phdthesis{guterl_modeling_2015, + title = {Modeling of hydrogen isotopes retention in plasma-facing components for fusion applications}, + abstract = {Plasma-material interactions might strongly affect plasma performances and life-time of future magnetic fusion devices. For example, retention and recycling of hydrogen isotopes in plasma-facing components (PFC) may lead to dynamics plasma-material interactions and significant accumulation of tritium in material. Understanding the multifaceted physics of hydrogen retention in PFC is thus crucial, but remains challenging due to the wide spectrum of retention processes on PFC surface (erosion, co- deposition, etc.) and in PFC bulk (trap sites, bubbles, etc.) induced by long-time exposure of PFC to high flux of energy and particles. In this context, we revisit in this work some aspects of the reaction-diffusion models used to describe retention of hydrogen implanted in material in fusion relevant. We first focus on the analysis of thermal desorption spectroscopy (TDS) experiments, showing that the evolution of hydrogen concentration in material during TDS experiments is usually quasi-static. An analytic description of thermal desorption spectra (TDSP) is then obtained in quasi-static regime and is used to highlight dependencies of TDSP on hydrogen retention parameters. The interpretation of Arrhenius plots to characterize hydrogen retention processes is then revisited. Moreover, it is shown that retention processes can be characterized using the shape of desorption peaks in TDSP, and that long desorption tails in TDSP can be used to estimate activation energy of diffusion of hydrogen in PFC. Hydrogen retention induced by a large number of different types of traps is examined next. A reaction-diffusion model of TDSP with a large number of types of traps is presented for the first time. The application of this model is illustrated on several experimental TDSP available in literature, which are consistently reproduced using several types of traps with a unique broad spectrum of detrapping energies. The values of these detrapping energies are shown to be in agreement with values predicted by density functional theory simulations when several hydrogen atoms are trapped in one material vacancy. Effects of surface processes on hydrogen retention and recycling are investigated in the second part. First, long-term outgassing of hydrogen from PFC during off-plasma events is considered. The super- diffusive power-law decay in time of the hydrogen outgassing flux is modeled with a revisited single trap reaction-diffusion model, showing that hydrogen outgassing is either surface-limited or diffusion-limited. The outgassing regime is shown to be governed either by processes in the bulk or on the surface of material. The influence of hydrogen concentration profiles in material on the power-law exponents is analyzed as well. Finally, the different models proposed in the literature to describe power-law decays of hydrogen outgassing flux experimentally observed during off-plasma events are reconciled. Hydrogen recombination and desorption on tungsten surface is investigated next using molecular dynamics (MD) and accelerated molecular dynamics simulations. Adsorption states, diffusion, hydrogen recombination into molecules, and clustering of hydrogen on tungsten surfaces are analyzed. It is shown that tungsten hydrogen interatomic potential, available in literature and used in MD simulations, cannot reproduce main features of hydrogen molecular recombination on tungsten surface. Hydrogen clustering on tungsten surface is nevertheless observed during MD simulations. Effects of hydrogen clustering on hydrogen desorption are thus analyzed by introducing a kinetic model describing the competition between surface diffusion, clustering and recombination. Different desorption regimes are identified, which reproduce some aspects of desorption regimes experimentally observed when tungsten surface is saturated with hydrogen}, language = {en}, - urldate = {2021-04-28}, - journal = {Nuclear Materials and Energy}, - author = {De Temmerman, Gregory and Heinola, Kalle and Borodin, Dmitriy and Brezinsek, Sebastijan and Doerner, Russell P. and Rubel, Marek and Fortuna-Zaleśna, Elżbieta and Linsmeier, Christian and Nishijima, Daisuke and Nordlund, Kai and Probst, Michael and Romazanov, Juri and Safi, Elnaz and Schwarz-Selinger, Thomas and Widdowson, Anna and Braams, Bastiaan J. and Chung, Hyun-Kyung and Hill, Christian}, - month = jun, - year = {2021}, - keywords = {Beryllium, Controlled fusion, Dust, Erosion–deposition, Plasma-facing material}, - pages = {100994}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BLTG9QN2\\S2352179121000740.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FIZVHXTA\\De Temmerman et al. - 2021 - Data on erosion and hydrogen fuel retention in Ber.pdf:application/pdf}, + school = {UC San Diego}, + author = {Guterl, Jérom̂e}, + year = {2015}, + keywords = {Molecular Dynamics, Macroscopic rate equations}, + file = {Guterl - 2015 - Modeling of hydrogen isotopes retention in plasma-.pdf:D\:\\Logiciels\\data_zotero\\storage\\AIX848SE\\Guterl - 2015 - Modeling of hydrogen isotopes retention in plasma-.pdf:application/pdf}, } -@article{kreter_linear_2015, - title = {Linear {Plasma} {Device} {PSI}-2 for {Plasma}-{Material} {Interaction} {Studies}}, - volume = {68}, - issn = {1536-1055}, - url = {https://doi.org/10.13182/FST14-906}, - doi = {10.13182/FST14-906}, - abstract = {The linear plasma device PSI-2 serves as a pilot experiment for the development of components, operational regimes and control systems for the linear plasma device JULE-PSI, which will be located in the nuclear environment allowing studies of radioactive and toxic samples. PSI-2 is also used for fusion reactor relevant plasma-material interaction studies. This contribution describes the PSI-2 layout and parameters and summarizes the recent scientific and technical progress in the project, including the installation of a target station for the sample manipulation and analyses.}, +@article{dethloff_modeling_2012, + title = {Modeling of helium bubble nucleation and growth in neutron irradiated boron doped {RAFM} steels}, + volume = {426}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311511010695}, + doi = {10.1016/j.jnucmat.2011.12.025}, + abstract = {Reduced activation ferritic/martensitic (RAFM) steels are promising candidates for structural materials in future fusion technology. In addition to other irradiation defects, the transmuted helium is believed to strongly influence material hardening and embrittlement behavior. A phenomenological model based on kinetic rate equations is developed to describe homogeneous nucleation and growth of helium bubbles in neutron irradiated RAFM steels. The model is adapted to different 10B doped EUROFER97 based heats, which already had been studied in past irradiation experiments. Simulations yield bubble size distributions, whereby effects of helium generation rate, surface energy, helium sinks and helium density are investigated. Peak bubble diameters under different conditions are compared to preliminary microstructural results on irradiated specimens. Helium induced hardening was calculated by applying the Dispersed Barrier Hardening model to simulated cluster size distributions. Quantitative microstructural investigations of unirradiated and irradiated specimens will be used to support and verify the model.}, + language = {en}, number = {1}, - urldate = {2021-05-19}, - journal = {Fusion Science and Technology}, - author = {Kreter, A. and Brandt, C. and Huber, A. and Kraus, S. and MÖller, S. and Reinhart, M. and Schweer, B. and Sergienko, G. and Unterberg, B.}, + urldate = {2019-10-31}, + journal = {Journal of Nuclear Materials}, + author = {Dethloff, Christian and Gaganidze, Ermile and Svetukhin, Vyacheslav V. and Aktaa, Jarir}, month = jul, - year = {2015}, - note = {Publisher: Taylor \& Francis -\_eprint: https://doi.org/10.13182/FST14-906}, - pages = {8--14}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QYPFSLTM\\FST14-906.html:text/html;Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D3Q2RAZV\\Kreter et al. - 2015 - Linear Plasma Device PSI-2 for Plasma-Material Int.pdf:application/pdf}, + year = {2012}, + keywords = {Cluster dynamics, Bubble}, + pages = {287--297}, + file = {Dethloff et al. - 2012 - Modeling of helium bubble nucleation and growth in.pdf:D\:\\Logiciels\\data_zotero\\storage\\D9Q4DBZX\\Dethloff et al. - 2012 - Modeling of helium bubble nucleation and growth in.pdf:application/pdf}, } -@article{weerasinghe_non-dilute_2020, - title = {Non-dilute helium-related defect interactions in the near-surface region of plasma-exposed tungsten}, - volume = {128}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/abs/10.1063/5.0023356}, - doi = {10.1063/5.0023356}, - number = {16}, - urldate = {2021-05-19}, - journal = {Journal of Applied Physics}, - author = {Weerasinghe, Asanka and Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, - month = oct, - year = {2020}, - note = {Publisher: American Institute of Physics}, - keywords = {mechanical properties}, - pages = {165109}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FPEFZ6GU\\5.html:text/html}, +@article{shimwell_multiphysics_2019, + title = {Multiphysics analysis with {CAD}-based parametric breeding blanket creation for rapid design iteration}, + volume = {59}, + copyright = {All rights reserved}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab0016}, + doi = {10.1088/1741-4326/ab0016}, + abstract = {Breeding blankets are designed to ensure tritium self-sufficiency in deuterium–tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. Blanket design is critical to the success of fusion reactors and integral to the design process. Neutronic simulations of breeder blankets are regularly performed to ascertain the performance of a particular design. An iterative process of design improvements and parametric studies are required to optimize the design and meet performance targets. Within the EU DEMO program the breeding blanket design cycle is repeated for each new baseline design. One of the key steps is to create three-dimensional models suitable primarily for use in neutronics, but could be used in other computer-aided design (CAD)-based physics and engineering analyses. This article presents a novel blanket design tool which automates the process of producing heterogeneous 3D CAD-based geometries of the helium-cooled pebble bed, water-cooled lithium lead, helium-cooled lithium lead and dual-coolant lithium lead blanket types. The paper shows a method of integrating neutronics, thermal analysis and mechanical analysis with parametric CAD to facilitate the design process. The blanket design tool described in this paper provides parametric geometry for use in neutronics and engineering simulations. This paper explains the methodology of the design tool and demonstrates use of the design tool by generating all four EU blanket designs using the EU DEMO baseline. Neutronics and heat transfer simulations using the models have been carried out. The approach described has the potential to considerably speed up the design cycle and greatly facilitate the integration of multiphysics studies.}, + language = {en}, + number = {4}, + journal = {Nuclear Fusion}, + author = {Shimwell, Jonathan and Delaporte-Mathurin, Rémi and Jaboulay, Jean-Charles and Aubert, Julien and Richardson, Chris and Bowman, Chris and Davis, Andrew and Lahiff, Andrew and Bernardi, James and Yasin, Sikander and Tang, Xiaoying}, + month = mar, + year = {2019}, + pages = {046019}, + file = {Shimwell et al. - 2019 - Multiphysics analysis with CAD-based parametric br.pdf:D\:\\Logiciels\\data_zotero\\storage\\PSZ49KMV\\Shimwell et al. - 2019 - Multiphysics analysis with CAD-based parametric br.pdf:application/pdf}, } -@article{weerasinghe_elastic_2020, - title = {Elastic {Properties} of {Plasma}-{Exposed} {Tungsten} {Predicted} by {Molecular}-{Dynamics} {Simulations}}, - volume = {12}, - issn = {1944-8244}, - url = {https://doi.org/10.1021/acsami.0c01381}, - doi = {10.1021/acsami.0c01381}, - abstract = {We report results of systematic molecular-dynamics computations of the elastic properties of single-crystalline tungsten containing structural defects, voids and overpressurized He nanobubbles, related to plasma exposure of tungsten serving as a plasma-facing component (PFC) in nuclear fusion devices. Our computations reveal that the empty voids are centers of dilatation resulting in the development of tensile stress in the tungsten matrix, whereas He-filled voids (nanobubbles) introduce compressive stress in the plasma-exposed tungsten. We find that the dependence of the elastic moduli of plasma-exposed tungsten, namely, the bulk, Young, and shear modulus, on its void fraction follows a universal exponential scaling relation. We also find that the elastic moduli of plasma-exposed tungsten soften substantially as a function of He content in the tungsten matrix, following an exponential scaling relation; this He-induced exponential softening is in addition to the softening caused in the matrix with increasing temperature. A systematic characterization of the dependence of the elastic moduli on the He bubble size reveals that He bubble growth significantly affects both the bulk modulus and the Poisson ratio of plasma-exposed tungsten, while its effect on the Young and shear moduli of the plasma-exposed material is weak. Our findings contribute directly to the development of a structure–property database that is required for the predictive modeling of the dynamical response of PFCs in nuclear fusion devices.}, - number = {19}, - urldate = {2021-05-19}, - journal = {ACS Applied Materials \& Interfaces}, - author = {Weerasinghe, Asanka and Wirth, Brian D. and Maroudas, Dimitrios}, +@article{frauenfelder_solution_1969, + title = {Solution and {Diffusion} of {Hydrogen} in {Tungsten}}, + volume = {6}, + issn = {0022-5355}, + url = {https://avs.scitation.org/doi/10.1116/1.1492699}, + doi = {10.1116/1.1492699}, + number = {3}, + urldate = {2019-10-07}, + journal = {Journal of Vacuum Science and Technology}, + author = {Frauenfelder, R.}, month = may, - year = {2020}, - note = {Publisher: American Chemical Society}, - keywords = {mechanical properties}, - pages = {22287--22297}, + year = {1969}, + keywords = {Experiment}, + pages = {388--397}, } -@article{chen_effects_2020, - title = {Effects of elastic softening and helium accumulation kinetics on surface morphological evolution of plasma-facing tungsten}, - volume = {61}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/abbf64}, - doi = {10.1088/1741-4326/abbf64}, - abstract = {Based on a continuous-domain model, capable of accessing the spatiotemporal scales relevant to fuzz formation on the surface of plasma-facing component (PFC) tungsten, we report self-consistent simulation results that elucidate the effects of elastic softening and helium (He) accumulation kinetics on the surface morphological response of PFC tungsten. The model accounts for the softening of the elastic moduli in the near-surface region of PFC tungsten, including both thermal softening at high temperature and softening due to He accumulation upon He implantation. The dependence of the elastic moduli on the He content follows an exponential scaling relation predicted by molecular-dynamics simulations, while the He content in the near-surface region of PFC tungsten evolves according to a first-order saturation kinetics, consistent with experimental and simulation results reported in the literature. We establish that this elastic softening accelerates both nanotendril growth on the PFC surface and the onset of fuzz formation. We also explore the role of the rate of He accumulation to a saturation level in the near-surface region of irradiated tungsten in the onset of fuzz formation. For PFC tungsten surfaces such as W(110) where, under typical irradiation conditions, the characteristic time scale for stress-driven surface diffusion is comparable to the characteristic time scale for He accumulation, we find that accelerating the rate of He accumulation accelerates the growth rate of nanotendrils emanating from the surface. Additionally, we present a systematic parametric study of the PFC surface morphological response to explore its dependence on the He accumulation kinetics that is controlled by the irradiation conditions for low-energy implantation. Finally, we introduce an incubation time for nanotendril growth on the PFC surface, a concept equivalent to that of incubation fluence discussed in the literature, to predict and explain the minimum exposure time required to observe fuzz formation on PFC tungsten surfaces.}, - language = {en}, - number = {1}, - urldate = {2021-05-19}, - journal = {Nuclear Fusion}, - author = {Chen, Chao-Shou and Dasgupta, Dwaipayan and Weerasinghe, Asanka and Wirth, Brian D. and Maroudas, Dimitrios}, +@article{anderl_deuterium_1999, + title = {Deuterium transport in {Cu}, {CuCrZr}, and {Cu}/{Be}}, + volume = {266-269}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311598008782}, + doi = {10.1016/S0022-3115(98)00878-2}, + abstract = {This paper presents the results of deuterium implantation/permeation experiments and TMAP4 simulations for a CuCrZr alloy, for OFHC-Cu and for a Cu/Be bi-layered structure at temperatures from 700 to 800 K. Experiments used a mass-analyzed, 3-keV D3+ ion beam with particle flux densities of 5×1019 to 7×1019 D/m2 s. Effective diffusivities and surface molecular recombination coefficients were derived giving Arrhenius pre-exponentials and activation energies for each material: CuCrZr alloy, (2.0×10−2 m2/s, 1.2 eV) for diffusivity and (2.9×x10−14 m4/s, 1.92 eV) for surface molecular recombination coefficients; OFHC Cu, (2.1×10−6 m2/s, 0.52 eV) for diffusivity and (9.1×10−18 m4/s, 0.99 eV) for surface molecular recombination coefficients. TMAP4 simulation of permeation data measured for a Cu/Be bi-layer sample was achieved using a four-layer structure (Cu/BeO interface/Be/BeO back surface) and recommended values for diffusivity and solubility in Be, BeO and Cu.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Anderl, R. A. and Hankins, M. R. and Longhurst, G. R. and Pawelko, R. J.}, + month = mar, + year = {1999}, + keywords = {Experiment}, + pages = {761--765}, + file = {Anderl et al. - 1999 - Deuterium transport in Cu, CuCrZr, and CuBe.pdf:D\:\\Logiciels\\data_zotero\\storage\\WXFLBVUE\\Anderl et al. - 1999 - Deuterium transport in Cu, CuCrZr, and CuBe.pdf:application/pdf}, +} + +@article{tsukatani_deuterium_2011, + title = {Deuterium {Retention} in {Damaged} {Tungsten}}, + volume = {60}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST11-A12727}, + doi = {10.13182/FST11-A12727}, + abstract = {In this research, thermal desorption characteristics of deuterium retained at trap sites of W created by irradiation of 300 keV hydrogen ions have been studied. With 10 hours of annealing, about 85\% of deuterium was desorbed at temperatures of 300 °C and 350 °C, while deuterium desorption at 250 °C was about 60\%. To estimate trapping energy of trap sites in this damaged W, TMAP simulation was performed. The result shows that the trapping energy of 1.29eV well accounted for the result of 250 °C annealing. In view that in the literature the vacancy trapping energy of hydrogen in tungsten was estimated to be close to 1.43 eV and the sensitivity analysis has given an uncertainty for the trapping energy of the order of 0.1 eV, it appears that the dominant trapping site type in the investigated damaged tungsten consists of vacancies.}, + number = {4}, + urldate = {2019-10-07}, + journal = {Fusion Science and Technology}, + author = {Tsukatani, K. and Ueda, Y. and Tanimoto, K. and Lee, H. T. and Ohtsuka, Y. and Taniguchi, M. and Inoue, T. and Sakamoto, K. and Takagi, I. and Yoshida, N.}, month = nov, - year = {2020}, - note = {Publisher: IOP Publishing}, - keywords = {mechanical properties}, - pages = {016016}, + year = {2011}, + keywords = {Experiment}, + pages = {1543--1547}, } -@article{wei_better_2020, - title = {A better nanochannel tungsten film in releasing helium atoms}, - volume = {532}, +@article{anderl_deuterium_1992, + title = {Deuterium {Transport} and {Trapping} in {Polycrystalline} {Tungsten}}, + volume = {21}, + issn = {0748-1896}, + url = {https://doi.org/10.13182/FST92-A29837}, + doi = {10.13182/FST92-A29837}, + abstract = {Deuterium permeation studies for polycrystalline tungsten foil have been conducted to provide data for estimating tritium transport and trapping in tungsten-clad divertors proposed for advanced fusion-reactor concepts. Based on a detailed transmission electron microscopy (TEM) microstructural characterization of the specimen material and on analyses of permeation data measured at temperatures ranging from 610 to 823 K for unannealed and annealed tungsten foil (25 µm thick), we note the following key results: (1) deuterium transport in tungsten foil is dominated by extensive trapping that varies inversely with prior anneal temperatures of the foil material, (2) the reduction in the trapped fraction correlates with a corresponding elimination of a high density of dislocations in cell-wall structures introduced during the foil fabrication process, (3) trapping behavior in these foils can be modelled using trap energies between 1.3 eV and 1.5 eV and trap densities ranging from 1 × 10−5 to 7 × 10−5 atom fraction.}, + number = {2P2}, + urldate = {2019-10-07}, + journal = {Fusion Technology}, + author = {Anderl, R. A. and Holland, D. F. and Longhurst, G. R. and Pawelko, R. J. and Trybus, C. L. and Sellers, C. H.}, + month = mar, + year = {1992}, + keywords = {Experiment}, + pages = {745--752}, +} + +@article{poon_flux_2002, + title = {Flux dependence of deuterium retention in single crystal tungsten}, + volume = {307-311}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311519311225}, - doi = {10.1016/j.jnucmat.2020.152044}, - abstract = {Discovering highly radiation resistant plasma facing materials (PFM) is an urgent target for nuclear fusion reactor. In our previous work, a new PFM (nanochannel tungsten film) that consists of many tungsten crystal columns was found having excellent radiation tolerant properties. In the present work, three tungsten columns whose top surfaces are \{100\}, \{110\} and \{111\} -oriented were studied by molecular dynamics simulations and density functional theory calculations. We find that the tungsten columns whose top surfaces are \{100\}-oriented retain fewer helium atoms than the tungsten columns whose top surfaces are \{110\} or \{111\}-oriented. Moreover, the microstructural changes of tungsten columns whose top surfaces are \{100\}-oriented are smaller than others after high helium fluence exposure, which indicates that the nanochannel tungsten film maybe more suitable than bulk tungsten for plasma facing material in releasing helium atoms and delaying the formation of “fuzz” structure. The results reported here can help us to design a better radiation resistant plasma facing material in the future.}, - language = {en}, - urldate = {2021-05-17}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311502009467}, + doi = {10.1016/S0022-3115(02)00946-7}, + abstract = {The retention of deuterium in single crystal tungsten has been measured as a function of the incident ion flux in the range of 1×1017–5×1019 D+/m2s at 300 K. Incident D3+ ions were implanted to fluences of 1021, 1022, and 1023 D+/m2 with ion energies (500 eV/D+) below the threshold energy for elastic collision damage. Above 3×1018 D+/m2s, little or no flux dependence is seen. However, a rapid decrease in retention is seen for incident fluxes below 1018 D+/m2s at the 1021 D+/m2 fluence, suggesting a threshold value below which retention is strongly reduced. Flux dependence at the higher fluences show a smaller decrease in retention with decreasing flux. The observed results are consistent with trapping and trap evolution by cluster and cavity formation. The effect of specimen surface preparation has proved to be very significant, especially for the lower fluence.}, + urldate = {2019-10-07}, journal = {Journal of Nuclear Materials}, - author = {Wei, Guo and Li, Jingwen and Li, Yonggang and Deng, Huiqiu and Jiang, Changzhong and Ren, Feng}, - month = apr, - year = {2020}, - pages = {152044}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Y45J6E62\\S0022311519311225.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HNIQ4AVZ\\Wei et al. - 2020 - A better nanochannel tungsten film in releasing he.pdf:application/pdf}, + author = {Poon, M. and Macaulay-Newcombe, R. G. and Davis, J. W. and Haasz, A. A.}, + month = dec, + year = {2002}, + keywords = {Experiment}, + pages = {723--728}, + file = {Poon et al. - 2002 - Flux dependence of deuterium retention in single c.pdf:D\:\\Logiciels\\data_zotero\\storage\\HF5GTHK7\\Poon et al. - 2002 - Flux dependence of deuterium retention in single c.pdf:application/pdf}, } -@article{wei_understanding_2019, - title = {Understanding the release of helium atoms from nanochannel tungsten: a molecular dynamics simulation}, - volume = {59}, - issn = {0029-5515}, - shorttitle = {Understanding the release of helium atoms from nanochannel tungsten}, - url = {https://doi.org/10.1088/1741-4326/ab14c7}, - doi = {10.1088/1741-4326/ab14c7}, - abstract = {The design of highly radiation-tolerant plasma-facing materials (PFMs) is of great importance for fusion reactors. Our recent experiments have shown that nanochannel tungsten (W) films have clearly superior radiation tolerance properties. In the present work, helium clustering and release from nanochannel tungsten were studied by molecular dynamics simulations. The effects of temperature and vacancy concentration on the helium release from a tungsten cylinder were investigated. Our results show that nanochannel W that consists of thin W cylinders releases He atoms more quickly than bulk W with flat surfaces, thus greatly reducing the He concentration and suppressing the formation and growth of He bubbles, which leads to increased radiation tolerance. Moreover, the microstructural changes due to increasing He fluence are smaller in nanochannel W than those in bulk W. Although vacancies in nanochannel W will trap He atoms, the nanochannel W also has a stronger tendency to stabilize helium retention than bulk W. The mechanism of helium release from nanochannel W was also examined. The results reported here are beneficial for guiding future work in the design of radiation resistant PFMs.}, - language = {en}, - number = {7}, - urldate = {2021-05-17}, - journal = {Nuclear Fusion}, - author = {Wei, Guo and Ren, Feng and Fang, Jingzhong and Hu, Wangyu and Gao, Fei and Qin, Wenjing and Cheng, Tao and Wang, Yongqiang and Jiang, Changzhong and Deng, Huiqiu}, - month = jun, - year = {2019}, - note = {Publisher: IOP Publishing}, - pages = {076020}, +@article{condon_hydrogen_1993, + title = {Hydrogen bubbles in metals}, + volume = {207}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/002231159390244S}, + doi = {10.1016/0022-3115(93)90244-S}, + abstract = {First a brief introduction to hydrogen bubbles in metals and their technological importance is presented. The review concentrates on those areas of bubble formation where the distinct chemical character of hydrogen is important. A distinction is made between nucleation and subsequent cavity growth mechanisms. Both homogeneous and heterogenous nucleation are given as possibilities. Three cavity growth mechanisms are delineated: plastic deformation near a surface referred to as “blistering”, plastic deformation by loop punching, and the collection of vacancy-hydrogen complexes. Several factors are considered which can determine the particular mechanism which applies, such as the source of the hydrogen and its concentration, solubility and diffusivity and the concentration of defects in the metal. A preemptive reaction to bubble formation is the one leading to metal hydride formation. This reaction must be considered both for predicting the formation of bubbles and for experimental observations. The possibility of plastic deformation near a free surface can lead to blistering, and this must be considered. The current understanding of loop punching processes is presented and applied to hydrogen bubble formation. Vacancy clustering may also lead to void formation which may then absorb further hydrogen-vacancy complexes. Illustrative examples of hydrogen filled cavities in selected metals and alloys are discussed in detail.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Condon, J. B. and Schober, T.}, + month = dec, + year = {1993}, + keywords = {Experiment}, + pages = {1--24}, + file = {Condon et Schober - 1993 - Hydrogen bubbles in metals.pdf:D\:\\Logiciels\\data_zotero\\storage\\7XTBMM2I\\Condon et Schober - 1993 - Hydrogen bubbles in metals.pdf:application/pdf}, } -@article{liu_major_2020, - title = {The major trap sites of deuterium in {CuCrZr} alloy}, - volume = {23}, +@article{yu_deuterium_2019, + title = {Deuterium retention in re-solidified tungsten and beryllium}, + volume = {18}, issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179120300314}, - doi = {10.1016/j.nme.2020.100755}, - abstract = {The energy characteristics of the main deuterium (D) traps in CuCrZr alloy samples, which were previously annealed at temperatures of 773, 873, 973 and 1073 K and then exposed to D2 gas at a pressure of 2.5 × 104 Pa and a temperature of 723 K for 10 h, were studied by thermal desorption spectroscopy. Samples of oxygen free copper (OFC) were also investigated in the same way. For OFC, annealing at 773 K could reduce D retention appreciably. It indicates the temperature of 773 K is high enough to reduce the total D amount trapped by intrinsic defects (i.e. vacancies, dislocations and grain boundaries). However, for CuCrZr alloy, heat treatment does not reduce the D retention significantly until the annealing temperature is higher than 1073 K. Scanning electron microscope (SEM) and energy dispersive spectrometer (EDS) observations show that the density of precipitate particles especially the Zr-rich precipitate particles increase for the 1073 K-annealed one. It suggests the dissolved Zr atoms in the substrate are responsible for the D retention in CuCrZr alloy. D detrapping energy from the dissolved Zr atoms in CuCrZr alloy is estimated to be 0.98 eV from the TDS measurements.}, - language = {en}, - urldate = {2021-05-26}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179118302436}, + doi = {10.1016/j.nme.2019.01.011}, + abstract = {Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads from edge localized modes (ELMs), and melting of the entire divertor surface will occur during vertical displacement events (VDEs) and disruptions. In addition, understanding tritium retention in plasma facing materials is critical for the successful operation of ITER due to safety reasons. Thus, the question of how melting affects hydrogenic retention is highly relevant for fusion devices. Here we use an Nd:YAG laser to melt tungsten and beryllium in vacuo, and the samples are subsequently exposed to deuterium plasma with sample temperatures ranging from 370 to 750 K. The deuterium content in re-solidified and reference (no laser) samples is measured using thermal desorption spectroscopy and modeled using TMAP-7. In all cases, the re-solidified samples have lower retention compared to the reference samples. For re-solidified tungsten, the most significant effect is in the 1.8 eV trap with peak thermal desorption temperature of ∼750 K, which had a 77\% reduction in the peak release rate compared with the reference sample. SEM imaging indicates that laser melting and re-solidification of tungsten anneals intrinsic defects that act as nucleation sites for larger-scale defects that develop during plasma exposure. However, melting does not significantly affect traps with lower de-trapping energies of 1.0 eV and 1.4 eV. In beryllium, melting and cracking results in lower retention compared to the reference sample by 40\%, and thermal desorption profiles indicate that the diffusion depth of deuterium into re-solidified beryllium is lower than that of the reference sample.}, + urldate = {2019-10-07}, journal = {Nuclear Materials and Energy}, - author = {Liu, Hao-Dong and Zhou, Hai-Shan and Zhao, Si-Xiang and Wang, Lu and Wei, Ran and Luo, Guang-Nan}, - month = may, - year = {2020}, - keywords = {Hydrogen isotope, CuCrZr alloy, Heat treatment, Retention}, - pages = {100755}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QUI9ESPI\\S2352179120300314.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z9XWYPEE\\Liu et al. - 2020 - The major trap sites of deuterium in CuCrZr alloy.pdf:application/pdf}, + author = {Yu, J. H. and Simmonds, M. J. and Baldwin, M. J. and Doerner, R. P.}, + month = jan, + year = {2019}, + keywords = {Experiment}, + pages = {297--306}, + annote = {These guys use TMAP7 for fitting TDS spectra minimising RMSD + manual bias}, + file = {Yu et al. - 2019 - Deuterium retention in re-solidified tungsten and .pdf:D\:\\Logiciels\\data_zotero\\storage\\8ZNLFRN8\\Yu et al. - 2019 - Deuterium retention in re-solidified tungsten and .pdf:application/pdf}, } -@article{baldwin_influence_2021, - title = {The influence of {D2} pressure on {D} retention and release from {Be} co-deposits}, +@article{ogorodnikova_deuterium_2003, + series = {Plasma-{Surface} {Interactions} in {Controlled} {Fusion} {Devices} 15}, + title = {Deuterium retention in tungsten in dependence of the surface conditions}, + volume = {313-316}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311502013752}, + doi = {10.1016/S0022-3115(02)01375-2}, + abstract = {The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter of the deuterium (D) retention database, new measurements of ion-driven D retention in polycrystalline W foil have been performed to clarify the mechanism of hydrogen isotope inventory in W. Deuterium retention has been investigated as a function of ion fluence, implantation temperature, incident energy and surface conditions. Special attention has been given on the investigation of D retention in thin films of tungsten carbide and tungsten oxide which can be formed on W surface in a fusion device. Such kinds of films increase the D retention in W. Several points are reviewed: (i) inventory in pure W, (ii) inventory in W pre-implanted by carbon ions and (iii) inventory in tungsten oxide.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Ogorodnikova, O. V and Roth, J and Mayer, M}, + month = mar, + year = {2003}, + keywords = {Experiment}, + pages = {469--477}, + file = {Ogorodnikova et al. - 2003 - Deuterium retention in tungsten in dependence of t.pdf:D\:\\Logiciels\\data_zotero\\storage\\LMRENIS9\\Ogorodnikova et al. - 2003 - Deuterium retention in tungsten in dependence of t.pdf:application/pdf}, +} + +@article{yajima_kinetics_2019, + title = {Kinetics of deuterium penetration into neutron-irradiated tungsten under exposure to high flux deuterium plasma}, + volume = {21}, issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S235217912100096X}, - doi = {10.1016/j.nme.2021.101023}, - abstract = {Beryllium co-deposit thermal desorption studies are reported that focus on the effect of D2 pressure during layer formation, as pressure has been linked in prior work to the formation of a high-retention-capacity sharp-release-feature. A pressure range from 0.3 to 13.3 Pa is explored. Additional insight into what drives the formation of T0 is established through co-deposit formation parameter variations including deposition temperature spanning 373 K to 608 K, and ion impact energy in the range 10-100 eV. It is found that the formation of the sharp release feature exhibits a multi-parameter dependence, but is predominately favored by low deposition temperature, higher D2 pressure, and to a small degree, increased ion impact energy, during deposition. TESSIM simulations of the D2 thermal release at the ITER bake temperatures of Tb1 (513 K) and Tb2 (623 K), show that the best efficacy for D removal (defined as the ratio of post to pre bake inventory) is found when the sharp release feature is present. However, when this feature is present, the total retained D inventory tends to be significantly increased.}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179118300516}, + doi = {10.1016/j.nme.2019.100699}, + abstract = {The objective of this study is to investigate the effects of neutron (n) irradiation on hydrogen isotope transport in tungsten (W). W samples were irradiated with neutrons in a fission reactor and then exposed to high flux deuterium (D) plasma at 563 K in a linear plasma device. The fraction of D release increased with increasing exposure time. In addition, the D retention in n-irradiated W increased in proportion to the square root of the plasma exposure time. These observations were explained by increase in the penetration depth of D with filling up displacement damages acting as strong trapping sites.}, language = {en}, - urldate = {2021-05-27}, + urldate = {2019-11-05}, journal = {Nuclear Materials and Energy}, - author = {Baldwin, M. J. and Založnik, A. and Simmonds, M. J. and Temmerman, G. De and Doerner, R. P.}, - month = may, - year = {2021}, - keywords = {Thermal desorption, Beryllium, Retention, Co-deposits}, - pages = {101023}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W83E6UEJ\\S235217912100096X.html:text/html}, + author = {Yajima, M. and Hatano, Y. and Ohno, N. and Kuwabara, T. and Toyama, T. and Takagi, M. and Suzuki, K.}, + month = dec, + year = {2019}, + keywords = {Experiment}, + pages = {100699}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5LCIY3YG\\Yajima et al. - 2019 - Kinetics of deuterium penetration into neutron-irr.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7DJ7A9CR\\S2352179118300516.html:text/html}, } -@article{markelj_deuterium_2020, - title = {Deuterium transport and retention in the bulk of tungsten containing helium: the effect of helium concentration and microstructure}, - volume = {60}, - issn = {0029-5515}, - shorttitle = {Deuterium transport and retention in the bulk of tungsten containing helium}, - url = {https://doi.org/10.1088/1741-4326/abadae}, - doi = {10.1088/1741-4326/abadae}, - abstract = {The effect of helium (He) on deuterium (D) retention and transport in the bulk of tungsten (W) was investigated. For this purpose samples were irradiated by 500 keV He ions at 300 K to different fluences in order to obtain He maximum concentrations of 1 at.\%, 3.4 at.\%, and 6.8 at.\% in 0.84 µm depth. In order to discern the effect of irradiation damage caused by He implantation from the effect of the pure He presence on D retention, the W samples were irradiated at 300 K by 20 MeV W ions in advance to create displacement damage in the crystal lattice to a damage dose of 0.23 dpa. The samples were exposed to a D atom beam at 600 K with a flux of 3.5 × 1018 D m−2s−1 to populate all the created defects. The D depth profiles were measured in situ during and at the end of exposure by nuclear reaction analysis to follow the dynamics of the D uptake. Thermal desorption spectra were collected ex situ at the end of the exposure. We show that D retention increases with implanted He fluence linearly following a D/He ratio of 0.29. We obtained peaking of D concentration at the position of maximum He concentration, reaching for the 6.8 at.\% He sample three times higher D concentration (1.1 at.\%) than obtained on high dpa W ion irradiated samples (0.37 at.\%) for the same loading conditions. D retention and transport was also studied on He-containing samples that were annealed to 1700 K. There was no reduction of D retention in the He zone but 80\% reduction in the only W irradiated zone was observed, meaning displacement damage was almost completely removed. In the He zone the D concentration increased to 1.35 at.\%, and we attribute this to trapping of D around He bubbles of 1.5 nm size created at the He peak maximum as obtained by transmission electron microscopy. Neither in the as He implanted nor the 1700 K annealed sample did He act as diffusion barrier. From this study we can conclude that in the main wall of a future fusion device the effect of He will not dominate D retention in W, but at high heat flux areas where displacement damage possibly anneals out He could accumulate in the material and it could eventually dominate over the effect of displacement damage.}, +@article{nagata_helium_2002, + title = {Helium and hydrogen trapping in {W} and {Mo} single-crystals irradiated by {He} ions}, + volume = {307-311}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311502012692}, + doi = {10.1016/S0022-3115(02)01269-2}, + abstract = {Retention of He and accumulation of H in the near surface layer of W and Mo single-crystals were studied during and after the implantation of He ions with 2–10 keV at 295 and 820 K. The He retention was saturated at a concentration of a He/metal ratio of about 0.25, depending on the implantation temperature. Subsequent He implantation caused H accumulation in the He saturated layer, up to a maximum concentration about equal to that of He. The initial H uptake rate just after the He irradiation was comparable to the impingement rate of the H2 or H2O molecule at the crystal surface from the residual gas. For the He irradiation at 820 K, blisters and exfoliation with large sizes were observed on the crystal surface, where impurities other than H and He were also enriched.}, language = {en}, - number = {10}, - urldate = {2021-05-27}, - journal = {Nuclear Fusion}, - author = {Markelj, S. and Schwarz-Selinger, T. and Pečovnik, M. and Chrominski, W. and Šestan, A. and Zavašnik, J.}, - month = sep, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {106029}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SJKD8JMA\\Markelj et al. - 2020 - Deuterium transport and retention in the bulk of t.pdf:application/pdf}, -} - -@misc{noauthor_integration_nodate, - title = {Integration issues on tritium management of the {European} {DEMO} {Breeding} {Blanket} and ancillary systems - {ScienceDirect}}, - url = {https://www-sciencedirect-com.insis.bib.cnrs.fr/science/article/pii/S0920379621003495?via%3Dihub}, - urldate = {2021-05-28}, - file = {Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\G3JAVNZ5\\S0920379621003495.html:text/html}, + urldate = {2019-11-04}, + journal = {Journal of Nuclear Materials}, + author = {Nagata, S. and Tsuchiya, B. and Sugawara, T. and Ohtsu, N. and Shikama, T.}, + month = dec, + year = {2002}, + keywords = {Experiment}, + pages = {1513--1516}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4WYNUQQ4\\Nagata et al. - 2002 - Helium and hydrogen trapping in W and Mo single-cr.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KPFK5N8I\\S0022311502012692.html:text/html}, } -@article{meschini_arc_2021, - title = {{ARC} reactor: {A} preliminary tritium environmental impact study}, - volume = {167}, - issn = {0920-3796}, - shorttitle = {{ARC} reactor}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379621001162}, - doi = {10.1016/j.fusengdes.2021.112340}, - abstract = {The fusion pilot power plant ARC is a conceptual design of a D–T Tokamak under investigation at the Massachusetts Institute of Technology. Special attention is paid on the radiological hazard, which until now has been translated in the reduction of materials activation. Indeed, one of ARC main goals is to be fast deployable in any US site: thus, the radiological risk associated to its presence must be minimized, both for the population and the environment. Tritium is one of the main sources of radiological hazard in ARC and it is almost ubiquitous: it is found in the vacuum chamber, in the blanket, in structural materials and in tritium processing and storing components. In this work, a safety analysis is proposed to quantify the radioactivity release following an accidental scenario. Tritium inventories in the main components are estimated starting from the preliminary design of the FLiBe circuit. The source term is quantified assuming the occurrence of a severe accident damaging key components. Afterward, the environmental impact and the doses to the most exposed individuals are evaluated through suitable population doses codes, and ARC compliance with safety limits is assessed.}, +@article{paul_dynamics_1995, + series = {Honour {Biography} {David} {Smith}}, + title = {On the dynamics of the reaction of positive hydrogen cluster ions ({H5}+ to {H23}+) with para and normal hydrogen at 10 {K}}, + volume = {149-150}, + issn = {0168-1176}, + url = {http://www.sciencedirect.com/science/article/pii/016811769504269Q}, + doi = {10.1016/0168-1176(95)04269-Q}, + abstract = {The dynamics of clustering and fragmentation reactions Hi+ + 2H2 ⇌ Hi+2+ + H2, for odd i, was studied at a nominal temperature of 10 K in a 22-pole radio-frequency ion trap in normal hydrogen and para-enriched hydrogen. Ternary association rate coefficients, k3, and binary fragmentation rate coefficients, kf, were extracted from the measured temporal evolution of the hydrogen cluster ion intensity, I(Hi+), for i = 3,⋯,23. Pure para hydrogen enhances the rate coefficients for association and fragmentation. For i {\textgreater} 9 this general trend is explained by a difference in the capture cross-sections, kc, for the two hydrogen nuclear spin modifications. Significant differences in k3 which remain for small clusters (i {\textless} 9) are due to the availability of the J = 1 rotational energy of the ortho modification when merging into the cluster. This surprising result is discussed in the framework of simple dynamical and energetic considerations. Possible structures of the cluster can be classified and estimates for the bond energy of the outermost H2 in the cluster as a function of cluster size are derived.}, language = {en}, - urldate = {2021-06-04}, - journal = {Fusion Engineering and Design}, - author = {Meschini, Samuele and Testoni, Raffaella and Segantin, Stefano and Zucchetti, Massimo}, - month = jun, - year = {2021}, - keywords = {Tritium, Safety, Tokamak, ARC reactor, Radiological release}, - pages = {112340}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2ZRJAF74\\Meschini et al. - 2021 - ARC reactor A preliminary tritium environmental i.pdf:application/pdf}, + urldate = {2019-10-30}, + journal = {International Journal of Mass Spectrometry and Ion Processes}, + author = {Paul, W. and Lücke, B. and Schlemmer, S. and Gerlich, D.}, + month = nov, + year = {1995}, + keywords = {Experiment}, + pages = {373--387}, + file = {Paul et al. - 1995 - On the dynamics of the reaction of positive hydrog.pdf:D\:\\Logiciels\\data_zotero\\storage\\LRBRMHHZ\\Paul et al. - 1995 - On the dynamics of the reaction of positive hydrog.pdf:application/pdf}, } -@article{lee_temperature-dependent_2021, - title = {Temperature-{Dependent} {Model} of {Helium} {Bubble} {Expansion} and {Bursting} in {Tungsten}}, +@article{grisolia_tritium_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Tritium absorption and desorption in {ITER} relevant materials: comparative study of tungsten dust and massive samples}, + volume = {463}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S002231152100324X}, - doi = {10.1016/j.jnucmat.2021.153101}, - abstract = {Continuum-scale models that can reliably predict the behavior of helium in tungsten are of interest to the fusion community due to the projected impact of these materials on fusion reactor operation. We perform molecular dynamics simulations of spherical helium bubbles of various sizes in tungsten at different temperatures and depths with the goal of determining a mathematical model of the pressure and density at which the bubbles initially expand or burst as a function of depth, size, temperature, and surface orientation. The bubbles are small enough that their loop-punching pressures cannot be accurately predicted with continuum mechanics, and their expansion behavior is important, as it appears to cause many of the features observed on helium-irradiated tungsten surfaces. We vary the temperature, bubble size, bubble depth, and surface orientation in each case, recording the bubble pressure and density that result in bubble expansion. An exponential function with three adjustable parameters is found to fit the results well; the parameters that best fit our results are provided.}, + shorttitle = {Tritium absorption and desorption in {ITER} relevant materials}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514007739}, + doi = {10.1016/j.jnucmat.2014.10.089}, + abstract = {Tritium adsorption and desorption from well characterized tungsten dust are presented. The dust used are of different types prepared by planetary milling and by aggregation technique in plasma. For the milled powder, the surface specific area (SSA) is 15.5m2/g. The particles are poly-disperse with a maximum size of 200nm for the milled powder and 100nm for the aggregation one. Prior to tritiation the particles are carefully de-oxidized. Both samples are experiencing a high tritium inventory from 5GBq/g to 35GBq/g. From comparison with massive samples and considering that tritium inventory increases with SSA, it is shown that surface effects are predominant in the tritium trapping process. Extrapolation to the ITER environment is undertaken with the help of a Macroscopic Rate Equation model. It is shown that, during the life time of ITER, these particles can exceed rapidly 1GBq/g.}, language = {en}, - urldate = {2021-06-02}, + urldate = {2019-10-25}, journal = {Journal of Nuclear Materials}, - author = {Lee, Brandon F. and Hammond, Karl D.}, - month = may, - year = {2021}, - keywords = {Bubble, Helium, Tungsten, Plasma-facing}, - pages = {153101}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4VLTBG2B\\S002231152100324X.html:text/html}, -} - -@article{montupet-leblond_permeation_2021, - title = {Permeation and trapping of hydrogen in {Eurofer97}}, - volume = {29}, - copyright = {All rights reserved}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121001290}, - doi = {10.1016/j.nme.2021.101062}, - abstract = {Diffusion and trapping of hydrogen isotopes in fusion materials need to be fully described in order to evaluate permeation and retention in fusion reactors walls and breeding blankets. Hydrogen gas permeation experiments have been conducted on Eurofer97 with pressures ranging from 101 to 105 Pa and temperatures between 473 K and 673 K, resulting in solubility K(T) (mol m−3 Pa−12)= 1.76⋅10−1exp(−0.27(eV)kBT), diffusivity D(T) (m2 s−1) =2.52⋅10−7exp(−0.16(eV)kBT) and permeability Φ(T) (mol m−1 Pa−12 s−1) =4.43⋅10−8exp(−0.43(eV)kBT). Trapping parameters have been investigated using thermal desorption spectrometry of deuterium-loaded samples coupled with parametric optimization, leading to detrapping energies Edt,1=0.51eV, Edt,2=1.27eV, Edt,3=1.65eV and densities Nt,1=6.01⋅1025 m−3, Nt,2=6.44⋅1022 m−3, Nt,3=3.88⋅1023 m−3. This parametric optimization is performed using a kinetic surface model: the contribution of this model is compared to the results given by solubility and recombination rate models.}, - journal = {Nuclear Materials and Energy}, - author = {Montupet-Leblond, Floriane and Hodille, E. A. and Vartanian, S. and Payet, M. and Delaporte-Mathurin, R. and Mougenot, J. and Charles, Y. and Bernard, E. and Grisolia, C.}, - month = dec, - year = {2021}, - keywords = {Hydrogen, Trapping, Permeation, Eurofer97, MHIMS, Surfaces, Thermal desorption spectrometry}, - pages = {101062}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JIXQCGKX\\S2352179121001290.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DC624WFY\\S2352179121001290.html:text/html;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EB7E997C\\S2352179121001290.html:text/html}, -} - -@article{schmidt_effects_2021, - title = {Effects of {Radiation}-{Induced} {Defects} on {Corrosion}}, - volume = {51}, - url = {https://doi.org/10.1146/annurev-matsci-080819-123403}, - doi = {10.1146/annurev-matsci-080819-123403}, - abstract = {The next generation of nuclear reactors will expose materials to conditions that, in some cases, are even more extreme than those in current fission reactors, inevitably leading to new materials science challenges. Radiation-induced damage and corrosion are two key phenomena that must be understood both independently and synergistically, but their interactions are often convoluted. In the light water reactor community, a tremendous amount of work has been done to illuminate irradiation-corrosion effects, and similar efforts are under way for heavy liquid metal and molten salt environments. While certain effects, such as radiolysis and irradiation-assisted stress corrosion cracking, are reasonably well established, the basic science of how irradiation-induced defects in the base material and the corrosion layer influence the corrosion process still presents many unanswered questions. In this review, we summarize the work that has been done to understand these coupled extremes, highlight the complex nature of this problem, and identify key knowledge gaps. Expected final online publication date for the Annual Review of Materials Science, Volume 51 is August 2021. Please see http://www.annualreviews.org/page/journal/pubdates for revised estimates.}, - number = {1}, - urldate = {2021-06-01}, - journal = {Annual Review of Materials Research}, - author = {Schmidt, Franziska and Hosemann, Peter and Scarlat, Raluca O. and Schreiber, Daniel K. and Scully, John R. and Uberuaga, Blas P.}, - year = {2021}, - note = {\_eprint: https://doi.org/10.1146/annurev-matsci-080819-123403}, - pages = {null}, + author = {Grisolia, C. and Hodille, E. and Chene, J. and Garcia-Argote, S. and Pieters, G. and El-Kharbachi, A. and Marchetti, L. and Martin, F. and Miserque, F. and Vrel, D. and Redolfi, M. and Malard, V. and Dinescu, G. and Acsente, T. and Gensdarmes, F. and Peillon, S. and Pegourié, B. and Rousseau, B.}, + month = aug, + year = {2015}, + keywords = {Experiment, Macroscopic rate equations}, + pages = {885--888}, + file = {Grisolia et al. - 2015 - Tritium absorption and desorption in ITER relevant.pdf:D\:\\Logiciels\\data_zotero\\storage\\TEFHUILY\\Grisolia et al. - 2015 - Tritium absorption and desorption in ITER relevant.pdf:application/pdf}, } -@article{shimada_overview_2012, - series = {Tenth {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-10)}, - title = {Overview of the {US}–{Japan} collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten}, - volume = {87}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379612001779}, - doi = {10.1016/j.fusengdes.2012.02.103}, - abstract = {The effect of neutron-irradiation damage has been mainly simulated using high-energy ion bombardment. A recent MIT report (PSFC/RR-10-4, An assessment of the current data affecting tritium retention and its use to project towards T retention in ITER, Lipschultz et al., 2010) summarizes the observations from high-energy ion bombardment studies and illustrates the saturation trend in deuterium concentration due to damage from ion irradiation in tungsten and molybdenum above 1 displacement per atom (dpa). While this prior database of results is quite valuable for understanding the behavior of hydrogen isotopes in plasma facing components (PFCs), it does not encompass the full range of effects that must be considered in a practical fusion environment due to short penetration depth, damage gradient, high damage rate, and high primary knock-on atom (PKA) energy spectrum of the ion bombardment. In addition, neutrons change the elemental composition via transmutations, and create a high radiation environment inside PFCs, which influences the behavior of hydrogen isotope in PFCs, suggesting the utilization of fission reactors is necessary for neutron-irradiation. Under the framework of the US–Japan TITAN program, tungsten samples (99.99at.\% purity from A.L.M.T. Co.) were irradiated by fission neutrons in the High Flux Isotope Reactor (HFIR), Oak Ridge National Laboratory (ORNL), at 50 and 300°C to 0.025, 0.3, and 2.4dpa, and the investigation of deuterium retention in neutron-irradiated tungsten was performed in the Tritium Plasma Experiment (TPE), the unique high-flux linear plasma facility that can handle tritium, beryllium and activated materials. This paper reports the recent results from the comparison of ion-damaged tungsten via various ion species (2.8MeV Fe2+, 20MeV W2+, and 700keV H−) with that from neutron-irradiated tungsten to identify the similarities and differences among them.}, +@incollection{ogorodnikova_trapping_2002, + address = {Dordrecht}, + series = {{NATO} {Science} {Series}}, + title = {Trapping {Effect} {In} {Hydrogen} {Retention} {In} {Metals}}, + isbn = {978-94-010-0444-2}, + abstract = {For the case of hydrogen interaction with a metal, modified equation for the timedependent change of trapped hydrogen has been derived. The present equation is essentially the same with previous models but slightly different in details, namely it is more general because covers all of previous models which are the particular cases of the present equation, it takes into account the difference in the structure of bcc and fcc metals, it does not include unknown parameters as in previous models such as attempt frequency (Wilson-Longhurst’s model) and trap radius (Myers-Doyle and Franzen’s models), but only well-known lattice parameter and diffusion coefficient from the literature. Comparison of the present model with Longhurst’s and Franzen’s models for hydrogen retention in tungsten shows that the present and Longhurst’s approaches differ by factor of six and Franzen’s approach results in about two orders of magnitude higher retention.}, language = {en}, - number = {7}, - urldate = {2021-06-09}, - journal = {Fusion Engineering and Design}, - author = {Shimada, Masashi and Hatano, Y. and Oya, Y. and Oda, T. and Hara, M. and Cao, G. and Kobayashi, M. and Sokolov, M. and Watanabe, H. and Tyburska-Püschel, B. and Ueda, Y. and Calderoni, P. and Okuno, K.}, - month = aug, - year = {2012}, - keywords = {Neutron-irradiation, Tungsten, Tritium retention, Ion-damage, Linear plasma device, Neutron}, - pages = {1166--1170}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2BVG2R8N\\S0920379612001779.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\B3BQPLD8\\Shimada et al. - 2012 - Overview of the US–Japan collaborative investigati.pdf:application/pdf}, + urldate = {2019-10-07}, + booktitle = {Hydrogen and {Helium} {Recycling} at {Plasma} {Facing} {Materials}}, + publisher = {Springer Netherlands}, + author = {Ogorodnikova, O. V.}, + editor = {Hassanein, Ahmed}, + year = {2002}, + doi = {10.1007/978-94-010-0444-2_2}, + keywords = {Macroscopic rate equations}, + pages = {7--15}, } -@misc{delaporte-mathurin_irfmdivhretention_2021, - title = {{IRFM}/{divHretention} source code {Github} repository https://github.com/{IRFM}/{divHretention}}, - copyright = {MIT}, - url = {https://github.com/IRFM/divHretention}, - abstract = {Tool to estimate H retention in tokamak divertors}, - urldate = {2021-06-17}, - publisher = {Institute for Magnetic Fusion Research}, - author = {Delaporte-Mathurin, Rémi and Dark, James and Yang, Hao and Hodille, E. A.}, - month = jun, - year = {2021}, - note = {original-date: 2021-02-02T15:25:50Z}, +@article{ohsawa_thermodynamics_2015, + title = {Thermodynamics of hydrogen-induced superabundant vacancy in tungsten}, + volume = {458}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514009714}, + doi = {10.1016/j.jnucmat.2014.12.029}, + abstract = {We investigate superabundant vacancy formation induced by hydrogen in tungsten in terms of an equilibrium thermodynamic model to estimate hydrogen isotope retention in plasma facing materials. Vacancy-hydrogen cluster concentrations in the bulk tungsten are calculated as a function of the H concentration at finite temperature. A monovacancy in usual bcc transition metals is capable of accommodating six H atoms, while a maximum of 12 H atoms can be accommodated in a tungsten monovacancy, according to first-principle calculations. The present results provide thermodynamic profiles of vacancy-hydrogen clusters trapping more than six H atoms for the first time. In present work, configurational transitions of H atoms trapped in the monovacancy and activation energies for them are investigated by examining the transition paths in order to calculate configurational entropy. Vacancy-hydrogen clusters trapping more than six H atoms exist in thermodynamic equilibrium. However, the major vacancy-hydrogen clusters are composed of six H atoms in a wide range of temperature and H concentration.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Ohsawa, Kazuhito and Nakamori, Fumihiro and Hatano, Yuji and Yamaguchi, Masatake}, + month = mar, + year = {2015}, + keywords = {Density Functional Theory}, + pages = {187--197}, + file = {Ohsawa et al. - 2015 - Thermodynamics of hydrogen-induced superabundant v.pdf:D\:\\Logiciels\\data_zotero\\storage\\J88THL3Y\\Ohsawa et al. - 2015 - Thermodynamics of hydrogen-induced superabundant v.pdf:application/pdf}, } -@article{imbeaux_design_2015, - title = {Design and first applications of the {ITER} integrated modelling \& analysis suite}, - volume = {55}, +@article{hodille_simulations_2017, + title = {Simulations of atomic deuterium exposure in self-damaged tungsten}, + volume = {57}, issn = {0029-5515}, - url = {https://doi.org/10.1088/0029-5515/55/12/123006}, - doi = {10.1088/0029-5515/55/12/123006}, - abstract = {The ITER Integrated Modelling \& Analysis Suite (IMAS) will support both plasma operation and research activities on the ITER tokamak experiment. The IMAS will be accessible to all ITER members as a key tool for the scientific exploitation of ITER. The backbone of the IMAS infrastructure is a standardized, machine-generic data model that represents simulated and experimental data with identical structures. The other outcomes of the IMAS design and prototyping phase are a set of tools to access data and design integrated modelling workflows, as well as first plasma simulators workflows and components implemented with various degrees of modularity.}, + doi = {10.1088/1741-4326/aa5aa5}, + abstract = {Simulations of deuterium (D) atom exposure in self-damaged polycrystalline tungsten at 500 K and 600 K are performed using an evolution of the MHIMS (migration of hydrogen isotopes in materials) code in which a model to describe the interaction of D with the surface is implemented. The surface-energy barriers for both temperatures are determined analytically with a steady-state analysis. The desorption energy per D atom from the surface is 0.69 ± 0.02 eV at 500 K and 0.87 ± 0.03 eV at 600 K. These values are in good agreement with ab initio calculations as well as experimental determination of desorption energies. The absorption energy (from the surface to the bulk) is 1.33 ± 0.04 eV at 500 K, 1.55 ± 0.02 eV at 600 K when assuming that the resurfacing energy (from the bulk to the surface) is 0.2 eV. Thermal-desorption spectrometry data after D atom exposure at 500 K and isothermal desorption at 600 K after D atom exposure at 600 K can be reproduced quantitatively with three bulk-detrapping energies, namely 1.65 ± 0.01 eV, 1.85 ± 0.03 eV and 2.06 ± 0.04 eV, in addition to the intrinsic detrapping energies known for undamaged tungsten (0.85 eV and 1.00 eV). Thanks to analyses of the amount of traps during annealing at different temperatures and ab initio calculations, the 1.65 eV detrapping energy is attributed to jogged dislocations and the 1.85 eV detrapping energy is attributed to dislocation loops. Finally, the 2.06 eV detrapping energy is attributed to D trapping in cavities based on literature reporting observations on the growth of cavities, even though this could also be understood as D desorbing from the C-D bond in the case of hydrocarbon contamination in the experimental sample.}, language = {en}, - number = {12}, - urldate = {2021-06-17}, + number = {5}, + urldate = {2019-10-07}, journal = {Nuclear Fusion}, - author = {Imbeaux, F. and Pinches, S. D. and Lister, J. B. and Buravand, Y. and Casper, T. and Duval, B. and Guillerminet, B. and Hosokawa, M. and Houlberg, W. and Huynh, P. and Kim, S. H. and Manduchi, G. and Owsiak, M. and Palak, B. and Plociennik, M. and Rouault, G. and Sauter, O. and Strand, P.}, - month = oct, - year = {2015}, - note = {Publisher: IOP Publishing}, - pages = {123006}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3D6BYZUC\\Imbeaux et al. - 2015 - Design and first applications of the ITER integrat.pdf:application/pdf}, + author = {Hodille, E. A. and Založnik, A. and Markelj, S. and Schwarz-Selinger, T. and Becquart, C. S. and Bisson, R. and Grisolia, C.}, + month = mar, + year = {2017}, + keywords = {Macroscopic rate equations}, + pages = {056002}, + file = {Hodille et al. - 2017 - Simulations of atomic deuterium exposure in self-d.pdf:D\:\\Logiciels\\data_zotero\\storage\\8CA3YWFD\\Hodille et al. - 2017 - Simulations of atomic deuterium exposure in self-d.pdf:application/pdf}, } -@article{schmid_use_2021, - title = {On the use of recombination rate coefficients in hydrogen transport calculations}, +@article{marian_recent_2017, + title = {Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions}, + volume = {57}, issn = {0029-5515}, - url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac07b2}, - doi = {10.1088/1741-4326/ac07b2}, - abstract = {The commonly accepted picture for the uptake of hydrogen isotopes (HIs) from the gas phase across the surface into a metal with an endothermic heat of solution for HIs is that of dissociation followed by thermalisation in a chemisorbed surface state and finally overcoming a surface barrier to enter the metal bulk where the HIs occupy interstitial solute sites. To leave the metal bulk the HIs first transition to the chemisorbed surface state from which they then enter gas phase by recombining into a diatomic molecule. This model is generally attributed to the work of Pick and Sonnenberg from 1985. They clearly distinguish surface states and subsurface solute sites where the recombination flux is proportional to the square of the concentration of chemisorbed atoms due the diatomic nature of this Langmuir–Hinshelwood process. In an effort to compare their extended model with an earlier surface model by Waelbroeck, which uses an expression for the recombination flux proportional to the square of the sub-surface interstitial solute concentration, they derive an effective recombination coefficient. However, also with the so-derived Pick and Sonnenberg recombination coefficient, the Waelbroeck model is only applicable under certain conditions. But, due to its simplicity, it is often used in boundary conditions of diffusion trapping type calculations, generally ignoring whether or not these conditions are met. This paper will use the full Pick and Sonnenberg model implemented in the TESSIM-X code and in simplified algebraic approximations, to show the limits of applicability of the Waelbroeck-Ansatz in modelling hydrogen transport in metals foreseen for the first wall of magnetic confinement fusion devices.}, + doi = {10.1088/1741-4326/aa5e8d}, + abstract = {Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, structural and plasma-facing materials will be exposed to unprecedented conditions of irradiation, heat flux, and temperature. While such extreme environments remain inaccessible experimentally, computational modeling and simulation can provide qualitative and quantitative insights into materials response and complement the available experimental measurements with carefully validated predictions. For plasma-facing components such as the first wall and the divertor, tungsten (W) has been selected as the leading candidate material due to its superior high-temperature and irradiation properties, as well as for its low retention of implanted tritium. In this paper we provide a review of recent efforts in computational modeling of W both as a plasma-facing material exposed to He deposition as well as a bulk material subjected to fast neutron irradiation. We use a multiscale modeling approach—commonly used as the materials modeling paradigm—to define the outline of the paper and highlight recent advances using several classes of techniques and their interconnection. We highlight several of the most salient findings obtained via computational modeling and point out a number of remaining challenges and future research directions.}, language = {en}, - urldate = {2021-06-15}, + number = {9}, + urldate = {2019-10-25}, journal = {Nuclear Fusion}, - author = {Schmid, Klaus and Zibrov, Mikhail}, - year = {2021}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\B34HU4YR\\Schmid et Zibrov - 2021 - On the use of recombination rate coefficients in h.pdf:application/pdf}, + author = {Marian, Jaime and Becquart, Charlotte S. and Domain, Christophe and Dudarev, Sergei L. and Gilbert, Mark R. and Kurtz, Richard J. and Mason, Daniel R. and Nordlund, Kai and Sand, Andrea E. and Snead, Lance L. and Suzudo, Tomoaki and Wirth, Brian D.}, + month = jun, + year = {2017}, + keywords = {Cluster dynamics, Density Functional Theory, Monte Carlo, Macroscopic rate equations}, + pages = {092008}, + file = {Marian et al. - 2017 - Recent advances in modeling and simulation of the .pdf:D\:\\Logiciels\\data_zotero\\storage\\6S8WXTGQ\\Marian et al. - 2017 - Recent advances in modeling and simulation of the .pdf:application/pdf}, } -@misc{delaporte-mathurin_divhretention_nodate, - title = {{divHretention}: {Tool} to estimate {H} retention in tokamak divertors, v0.1.3 {PyPi} distribution}, - copyright = {MIT License}, - shorttitle = {{divHretention}}, - url = {https://pypi.org/project/divHretention/}, - urldate = {2021-06-18}, - author = {Delaporte-Mathurin, Remi}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4WKYK3W2\\divHretention.html:text/html}, +@article{matveev_reaction-diffusion_2018, + title = {Reaction-diffusion modeling of hydrogen transport and surface effects in application to single-crystalline {Be}}, + volume = {430}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X18303537}, + doi = {10.1016/j.nimb.2018.05.037}, + abstract = {A model based on a reaction-diffusion approach is used to simulate thermal desorption experiments performed with ion beam exposed single-crystalline beryllium. The model describes deuterium retention, migration and release, relating microscopic material properties to desorption spectra observed in experiments. Multiple trapping at single vacancies, hydrogen accumulation on the surface and surface coverage dependent desorption are accounted for in the model, showing good qualitative agreement with experimental observations.}, + language = {en}, + urldate = {2019-10-29}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Matveev, D. and Wensing, M. and Ferry, L. and Virot, F. and Barrachin, M. and Ferro, Y. and Linsmeier, Ch.}, + month = sep, + year = {2018}, + keywords = {Macroscopic rate equations}, + pages = {23--30}, + file = {Matveev et al. - 2018 - Reaction-diffusion modeling of hydrogen transport .pdf:D\:\\Logiciels\\data_zotero\\storage\\XNWMCIL5\\Matveev et al. - 2018 - Reaction-diffusion modeling of hydrogen transport .pdf:application/pdf}, } -@article{fan_impact_2021, - title = {Impact of helium irradiation on the crystallographic orientation change in single-crystalline tungsten {\textbackslash}ast}, - volume = {61}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/abff04}, - doi = {10.1088/1741-4326/abff04}, - abstract = {Understanding the helium effects on the surface modifications of tungsten is of great interest and significance for developing plasma-facing materials. Our recent studies revealed that the ion irradiation of helium at room temperature produces 〈111〉-oriented surface grains in single-crystalline tungsten 100 and 110, which may play an important role in the surface and subsurface evolutions of tungsten subjected to fusion-relevant service environments. Although the driving force for the formation of surface grains is well explained by ion channeling effect, the underlying formation mechanism remains unclear. In this work, we investigated the orientation relationship between irradiation-induced new surface grains and single-crystalline tungsten matrix. The experimental results of electron backscatter diffraction demonstrated that the formation of most 〈111〉-oriented surface grains in both helium-irradiated tungsten 100 or 110 can be regarded as the grain rotation of matrix around its in-plane 〈110〉 axis.}, +@article{bonnin_rate_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Rate equations modeling for hydrogen inventory studies during a real tokamak material thermal cycle}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514007375}, + doi = {10.1016/j.jnucmat.2014.10.053}, + abstract = {Prediction and control of tritium inventory in plasma-facing components (PFCs) is a critical nuclear safety issue for ITER and future fusion devices. This goal can be achieved through rate equations models as presented here. We calibrate our models with thermal desorption spectrometry results to obtain a validated set of material parameters relevant to hydrogen inventory processes in bulk tungsten. The best fits are obtained with two intrinsic trap types, deep and shallow, and an extrinsic trap created by plasma irradiation and plastic deformation of the tungsten matrix associated with blister formation. We then consider a realistic cycle of plasma discharges consisting of 400s of plasma exposure followed by a resting period of 1000s, repeating for several hours. This cycle is then closed by a long “overnight” period, thus providing an estimate of the amount of tritium retained in the PFCs after a full day of standard operation.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Bonnin, X. and Hodille, E. and Ning, N. and Sang, C. and Grisolia, Ch.}, + month = aug, + year = {2015}, + keywords = {Macroscopic rate equations}, + pages = {970--973}, + file = {Bonnin et al. - 2015 - Rate equations modeling for hydrogen inventory stu.pdf:D\:\\Logiciels\\data_zotero\\storage\\PNSWKRZY\\Bonnin et al. - 2015 - Rate equations modeling for hydrogen inventory stu.pdf:application/pdf}, +} + +@article{benannoune_numerical_2019, + title = {Numerical simulation by finite element modelling of diffusion and transient hydrogen trapping processes in plasma facing components}, + volume = {19}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179118301169}, + doi = {10.1016/j.nme.2019.01.023}, + abstract = {In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures full 3D Macroscopic Rate Equation (MRE) modelling is proposed based on a finite element method (FEM). The model, implemented in the 3DS Abaqus software, uses a generalized transport equation, which accounts for mechanical fields, hydrogen transport and trapping, and their evolution with time. The influence of a-priori known thermal field has also been included. To ensure the solution convergence and the numerical stability, the trapping kinetic is introduced by using an approximation of the analytical solution the McNabb and Foster equation. Comparisons with a relevant 1D MRE code and with thermal programmed desorption (TPD) experimental results are performed on a 1D configuration to validate the model. Next, the model is used to simulate the tritium diffusion and trapping in a 2D geometry of interest in the upper plug of ITER tokamak, and results of tritium inventory are compared with an equivalent 1D calculation.}, + urldate = {2019-10-07}, + journal = {Nuclear Materials and Energy}, + author = {Benannoune, S. and Charles, Y. and Mougenot, J. and Gaspérini, M. and De Temmerman, G.}, + month = may, + year = {2019}, + keywords = {Macroscopic rate equations}, + pages = {42--46}, + file = {Benannoune et al. - 2019 - Numerical simulation by finite element modelling o.pdf:D\:\\Logiciels\\data_zotero\\storage\\T99M696W\\Benannoune et al. - 2019 - Numerical simulation by finite element modelling o.pdf:application/pdf}, +} + +@article{sang_modelling_2014, + series = {Proceedings of the 11th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-11 ({ISFNT}-11) {Barcelona}, {Spain}, 15-20 {September}, 2013}, + title = {Modelling of hydrogen isotope retention in the tungsten divertor of {EAST} during {ELMy} {H}-mode}, + volume = {89}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379614000416}, + doi = {10.1016/j.fusengdes.2014.01.040}, + abstract = {In this work, we study hydrogen isotopes (HI) inventory inside tungsten plasma-facing materials during high confinement mode discharges with repetitive edge localized modes (ELMy H-mode) based on the operating parameters of the EAST device, since tungsten is considered as the primary plasma-facing material and the ELMy H-mode is an important operation regime for EAST and future devices. The upgraded Hydrogen Isotope Inventory Processes Code (HIIPC) is applied with the incident depth profile provided by SRIM-2013 to make the study. The code is first verified by comparison with experimental measurements. The effects of the incident ion energy and ion flux on the retention are then studied. Finally, using the parameters obtained from EAST diagnostics, the HI retention inside the W divertor during ELMy H-mode is studied, which indicates the retained HI can be increased dramatically mainly due to ion-induced trap sites by ELMs.}, language = {en}, - number = {7}, - urldate = {2021-06-18}, - journal = {Nuclear Fusion}, - author = {Fan, Cuncai and Katoh, Yutai and Hu, Xunxiang}, - month = jun, - year = {2021}, - note = {Publisher: IOP Publishing}, - pages = {076011}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\URV3P6F9\\Fan et al. - 2021 - Impact of helium irradiation on the crystallograph.pdf:application/pdf}, + number = {9}, + urldate = {2019-10-30}, + journal = {Fusion Engineering and Design}, + author = {Sang, Chaofeng and Sun, Jizhong and Bonnin, Xavier and Wang, Liang and Du, Hailong and Huang, Yan and Wang, Dezhen}, + month = oct, + year = {2014}, + keywords = {Macroscopic rate equations}, + pages = {2214--2219}, + file = {Sang et al. - 2014 - Modelling of hydrogen isotope retention in the tun.pdf:D\:\\Logiciels\\data_zotero\\storage\\STBIKPXD\\Sang et al. - 2014 - Modelling of hydrogen isotope retention in the tun.pdf:application/pdf}, } -@article{hodille_modelling_2021, - title = {Modelling tritium adsorption and desorption from tungsten dust particles with a surface kinetic model}, +@article{sang_modelling_2012, + title = {Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices}, + volume = {52}, issn = {0029-5515}, - url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac0f37}, - doi = {10.1088/1741-4326/ac0f37}, - abstract = {A kinetic surface model is presented and used to explain the loading and desorption kinetics of tritium retained in micrometre-sized tungsten (W) dust particles. The model describes the sticking of hydrogen isotopes from the gas phase to W surfaces and the desorption from W surfaces. The initial sticking coefficient is set to one and independent of the temperature. The activation energy for desorption depends on the hydrogen coverage of the surface and is parametrised with density functional theory (DFT) calculations for W(100), W(110), and W(111) surface. The DFT-parametrised model is successfully compared to experimental results showing that the amount of measured tritium as well as the desorption kinetic can be modelled with only tritium adsorbed on the surface of W dust particles. Then, the model is used to explore possible scenarios to remove the tritium from the W surfaces by exposing the tritiated surfaces to either deuterium and hydrogen. The simulations suggest that it can be possible to remove all the tritium trapped on the W surfaces even at room temperature as soos as the hydrogen or deuterium pressure is higher than the tritium pressure. This gives opportunity to build tritium removal scenarios for ITER.}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/52/4/043003}, + doi = {10.1088/0029-5515/52/4/043003}, + abstract = {Hydrogen isotope inventory (HII) is a key issue for fusion devices such as ITER. Simultaneous use of Be, W and C as the wall material for different parts of plasma-facing components (PFCs) will bring in material mixing issues, which compound that of hydrogen isotope retention. To simulate the hydrogen inventory in the PFCs, we have developed a flexible standalone model called HIIPC (Hydrogen Isotope Inventory Processes Code). The particle-balance-based model for reaction–diffusion and HII in metal and porous media (mainly carbon and co-deposited layers) is presented, coupled with a heating model which can calculate the temperature distribution. Some sample results are given to illustrate the model's capabilities and show good qualitative agreement with the experiment.}, language = {en}, - urldate = {2021-06-29}, + number = {4}, journal = {Nuclear Fusion}, - author = {Hodille, Etienne Augustin and Payet, Mickael and Marascu, Valentina and Peillon, Samuel and Mougenot, Jonathan and Ferro, Yves and Delaporte-Mathurin, Rémi and Leblond, Floriane and Bernard, Elodie and Grisolia, Christian}, - year = {2021}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D9LARE6K\\Hodille et al. - 2021 - Modelling tritium adsorption and desorption from t.pdf:application/pdf}, + author = {Sang, Chaofeng and Bonnin, Xavier and Warrier, Manoj and Rai, Abha and Schneider, Ralf and Sun, Jizhong and Wang, Dezhen}, + month = mar, + year = {2012}, + keywords = {Macroscopic rate equations}, + pages = {043003}, + file = {Sang et al. - 2012 - Modelling of hydrogen isotope inventory in mixed m.pdf:D\:\\Logiciels\\data_zotero\\storage\\4836Z5VL\\Sang et al. - 2012 - Modelling of hydrogen isotope inventory in mixed m.pdf:application/pdf}, } -@article{zaloznik_deuterium_2020, - title = {Deuterium removal from beryllium co-deposits by simulated strike-point sweeping}, - volume = {24}, +@article{matveev_modeling_2019, + title = {Modeling of {H}/{D} isotope-exchange in crystalline beryllium}, + volume = {20}, issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179120300260}, - doi = {10.1016/j.nme.2020.100750}, - abstract = {Beryllium (Be) co-deposition with hydrogen isotopes will probably be the main mechanism of tritium accumulation in ITER. To reduce the use of baking of the first wall and divertor, raising strike-points during a pure deuterium (D) discharge has been proposed to heat the co-deposits directly and enhance tritium desorption. The feasibility of such plasma-induced removal as a potential means of tritium control has been investigated. Be-D co-deposited layers with a thickness of around 3 μm were created at 428–458 K and exposed to D or H plasma at various temperatures (673–873 K) for various times (180–1200 s). The remaining D content was measured by thermal desorption spectroscopy and compared to the control samples. Plasma-induced desorption was found to be efficient in removing significant amounts of D out of the co-deposits, removing 85\% of D from the layer after D plasma exposure at 773 K for 1200 s and 84\% of D after exposure at 873 K for only 180 s.}, - language = {en}, - urldate = {2021-06-29}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179118302655}, + doi = {10.1016/j.nme.2019.100682}, + abstract = {A reaction-diffusion model with surface occupation dependent desorption [D. Matveev et al., Nucl. Instr. Meth. B 430 (2018) 23–30] has been updated to handle multiple hydrogen species to simulate hydrogen/deuterium isotope-exchange experiments performed on polycrystalline beryllium samples under ultra-high vacuum laboratory conditions. In the experiments subsequent exposures of a sample to hydrogen and deuterium ion beams in direct and reverse implantation order were followed by thermal desorption spectroscopy measurements under a constant heating rate of 0.7 K/s. The recorded signals of masses 2 to 4 (H2, HD and D2) indicate that the second implanted isotope dominates clearly the low temperature release stage ( ≈ 450 K), while both isotopes show a comparable contribution to the high temperature desorption stage ( ≈ 700 K) with only minor effect of the implantation order attributed to a slightly deeper penetration of deuterium compared to hydrogen. Simulations of the implantation and subsequent thermal desorption of hydrogen isotopes are performed to assess the atomic processes behind the isotope-exchange. Simulations were performed under the assumption that the low temperature release stage is attributed to hydrogen/deuterium atoms retained on effective open surfaces (e.g. interconnected porosity) represented in the simulations by a surface with an effective surface area exceeding the nominal exposed surface area by a factor up to 100. Kinetic de-trapping from vacancies with multiple trapping levels and enhanced desorption at surface coverages close to saturation are addressed in the model as possible mechanisms promoting the isotope-exchange. Simulation results suggest the applicability of the model to describe isotope-exchange processes in crystalline beryllium and give a qualitative explanation of the observed experimental facts.}, + urldate = {2019-10-11}, journal = {Nuclear Materials and Energy}, - author = {Založnik, Anže and Doerner, Russell P. and De Temmerman, Gregory}, + author = {Matveev, D. and Hansen, P. and Dittmar, T. and Koslowski, H. R. and Linsmeier, Ch.}, month = aug, - year = {2020}, - keywords = {Deuterium, Beryllium co-deposits, Tritium removal}, - pages = {100750}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5H2UMUJF\\S2352179120300260.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VZEWE7VS\\Založnik et al. - 2020 - Deuterium removal from beryllium co-deposits by si.pdf:application/pdf}, + year = {2019}, + keywords = {Macroscopic rate equations}, + pages = {100682}, + file = {Matveev et al. - 2019 - Modeling of HD isotope-exchange in crystalline be.pdf:D\:\\Logiciels\\data_zotero\\storage\\DATVZ54C\\Matveev et al. - 2019 - Modeling of HD isotope-exchange in crystalline be.pdf:application/pdf}, } -@article{kuang_divertor_2020, - title = {Divertor heat flux challenge and mitigation in {SPARC}}, - volume = {86}, - issn = {0022-3778, 1469-7807}, - url = {https://www.cambridge.org/core/journals/journal-of-plasma-physics/article/divertor-heat-flux-challenge-and-mitigation-in-sparc/A25A8CFADBBA33AD9AAC18F24E40A18E}, - doi = {10.1017/S0022377820001117}, - abstract = {Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m−2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections ({\textasciitilde}11–34 MJ m−2) are comparable with those for ITER. However, the relatively short pulse length ({\textasciitilde}25 s pulse, with a {\textasciitilde}10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a {\textasciitilde}1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.}, +@article{hodille_macroscopic_2015, + title = {Macroscopic rate equation modeling of trapping/detrapping of hydrogen isotopes in tungsten materials}, + volume = {467}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311515300660}, + doi = {10.1016/j.jnucmat.2015.06.041}, + abstract = {Relevant parameters for trapping of Hydrogen Isotopes (HIs) in polycrystalline tungsten are determined with the MHIMS code (Migration of Hydrogen Isotopes in MaterialS) which is used to reproduce Thermal Desorption Spectrometry experiments. Three types of traps are found: two intrinsic traps (detrapping energy of 0.87 eV and 1.00 eV) and one extrinsic trap created by ion irradiation (detrapping energy of 1.50 eV). Then MHIMS is used to simulate HIs retention at different fluences and different implantation temperatures. Simulation results agree well with experimental data. It is shown that at 300 K the retention is limited by diffusion in the bulk. For implantation temperatures above 500 K, the retention is limited by trap creation processes. Above 600 K, the retention drops by two orders of magnitude as compared to the retention at 300 K. With the determined detrapping energies, HIs outgassing at room temperature is predicted. After ions implantation at 300 K, 45\% of the initial retention is lost to vacuum in 300 000 s while during this time the remaining trapped HIs diffuse twice as deep into the bulk.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Hodille, E. A. and Bonnin, X. and Bisson, R. and Angot, T. and Becquart, C. S. and Layet, J. M. and Grisolia, C.}, + month = dec, + year = {2015}, + keywords = {Macroscopic rate equations}, + pages = {424--431}, + file = {Hodille et al. - 2015 - Macroscopic rate equation modeling of trappingdet.pdf:D\:\\Logiciels\\data_zotero\\storage\\MB4IWHZA\\Hodille et al. - 2015 - Macroscopic rate equation modeling of trappingdet.pdf:application/pdf}, +} + +@article{humrickhouse_implementation_2011, + title = {Implementation of {Tritium} {Permeation} {Models} in the {CFD} {Code} {Fluent}}, + volume = {60}, + issn = {1536-1055}, + doi = {10.13182/FST11-A12732}, + abstract = {A number of additions have been made to the computational fluid dynamics (CFD) code Fluent in order to model hydrogen permeation. In addition to fluid dynamics, Fluent solves for heat transfer in coupled solid and fluid regions, and solves advection-diffusion equations for scalar quantities such as hydrogen concentration. The latter have been modified with additional code to satisfy Sievert’s Law at solid-fluid interfaces and allow for temperature dependent diffusivity and permeability.The method has been employed to model the Tritium Heat Exchanger (THX) experiment at INL, which investigates hydrogen permeation in helium and candidate structural materials for high temperature gas reactor heat exchangers. The Arrhenius law parameters used in Fluent for Inconel 617 are initially determined via a simplified analytical method, and the resulting model predictions compare favorably with experiment data.}, + number = {4}, + urldate = {2019-10-23}, + journal = {Fusion Science and Technology}, + author = {Humrickhouse, P. W. and Calderoni, P. and Merrill, B. J.}, + month = nov, + year = {2011}, + keywords = {Macroscopic rate equations}, + pages = {1564--1567}, +} + +@article{simmonds_expanding_2018, + title = {Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning: {Applied} to hydrogen uptake and release from tungsten}, + volume = {508}, + issn = {0022-3115}, + shorttitle = {Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311517315301}, + doi = {10.1016/j.jnucmat.2018.05.080}, + abstract = {Simulating the implantation and thermal desorption evolution in a reaction-diffusion model requires solving a set of coupled differential equations that describe the trapping and release of atomic species in Plasma Facing Materials (PFMs). These fundamental equations are well outlined by the Tritium Migration Analysis Program (TMAP) which can model systems with no more than three active traps per atomic species. To overcome this limitation, we have developed a Pseudo Trap and Temperature Partition (PTTP) scheme allowing us to lump multiple inactive traps into one pseudo trap, simplifying the system of equations to be solved. For all temperatures, we show the trapping of atoms from solute is exactly accounted for when using a pseudo trap. However, a single effective pseudo trap energy can not well replicate the release from multiple traps, each with its own detrapping energy. However, atoms held in a high energy trap will remain trapped at relatively low temperatures, and thus there is a temperature range in which release from high energy traps is effectively inactive. By partitioning the temperature range into segments, a pseudo trap can be defined for each segment to account for multiple high energy traps that are actively trapping but are effectively not releasing atoms. With increasing temperature, as in controlled thermal desorption, the lowest energy trap is nearly emptied and can be removed from the set of coupled equations, while the next higher energy trap becomes an actively releasing trap. Each segment is thus calculated sequentially, with the last time step of a given segment solution being used as an initial input for the next segment as only the pseudo and actively releasing traps are modeled. This PTTP scheme is then applied to experimental thermal desorption data for tungsten (W) samples damaged with heavy ions, which display six distinct release peaks during thermal desorption. Without modifying the TMAP7 source code the PTTP scheme is shown to successfully model the D retention in all six traps. We demonstrate the full reconstruction from the plasma implantation phase through the controlled thermal desorption phase with detrapping energies near 0.9, 1.1, 1.4, 1.7, 1.9 and 2.1 eV for a W sample damaged at room temperature.}, language = {en}, - number = {5}, - urldate = {2021-06-28}, - journal = {Journal of Plasma Physics}, - author = {Kuang, A. Q. and Ballinger, S. and Brunner, D. and Canik, J. and Creely, A. J. and Gray, T. and Greenwald, M. and Hughes, J. W. and Irby, J. and LaBombard, B. and Lipschultz, B. and Lore, J. D. and Reinke, M. L. and Terry, J. L. and Umansky, M. and Whyte, D. G. and Wukitch, S. and Team, the SPARC}, - month = oct, - year = {2020}, - note = {Publisher: Cambridge University Press}, - keywords = {fusion plasma, plasma devices}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JDTJ42TK\\A25A8CFADBBA33AD9AAC18F24E40A18E.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZYVDDGA2\\Kuang et al. - 2020 - Divertor heat flux challenge and mitigation in SPA.pdf:application/pdf}, + urldate = {2019-11-07}, + journal = {Journal of Nuclear Materials}, + author = {Simmonds, M. J. and Yu, J. H. and Wang, Y. Q. and Baldwin, M. J. and Doerner, R. P. and Tynan, G. R.}, + month = sep, + year = {2018}, + keywords = {Macroscopic rate equations}, + pages = {472--480}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EP497L3V\\Simmonds et al. - 2018 - Expanding the capability of reaction-diffusion cod.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2SMMZLR6\\S0022311517315301.html:text/html}, } -@article{lasa_multi-physics_2020, - title = {Multi-physics modeling of the long-term evolution of helium plasma exposed surfaces}, - volume = {T171}, +@article{hodille_estimation_2017, + title = {Estimation of the tritium retention in {ITER} tungsten divertor target using macroscopic rate equations simulations}, + volume = {T170}, issn = {1402-4896}, - url = {https://doi.org/10.1088/1402-4896/ab4c29}, - doi = {10.1088/1402-4896/ab4c29}, - abstract = {In this manuscript we introduce a simulation tool-suite for predicting plasma-surface interactions (PSI), which aims to predict the evolution of the plasma-facing surfaces that continually change due to exposure to fusion plasmas. A comprehensive description of PSI involves a wide range of physical phenomena, of which we include components for (a) the gas implantation and its dynamic evolution below the divertor surface; (b) erosion of wall material; (c) transport and re-deposition of the eroded impurities; and (d) the scrape-off layer plasma including fuel ions and extrinsic impurities. These components are integrated to predict changes in surface morphology and fuel recycling, and the effect of material erosion and re-deposition in fuel retention. Integrated simulations for ITER-like parameters in a helium plasma environment are presented, focused on the response of the tungsten divertor. The model is also applied to predicting the response of the tungsten surface pre-damaged by He plasma, to burning plasma operations. This case further demonstrates the capability to model the effect of sub-surface helium dynamics, which include helium nucleation, clustering and the bursting of over-pressurized bubbles, its impact on fuel recycling as well as the effect of sputtering on the surface evolution.}, + doi = {10.1088/1402-4896/aa8787}, + abstract = {Based on macroscopic rate equation simulations of tritium migration in an actively cooled tungsten (W) plasma facing component (PFC) using the code MHIMS (migration of hydrogen isotopes in metals), an estimation has been made of the tritium retention in ITER W divertor target during a non-uniform exponential distribution of particle fluxes. Two grades of materials are considered to be exposed to tritium ions: an undamaged W and a damaged W exposed to fast fusion neutrons. Due to strong temperature gradient in the PFC, Soret effect’s impacts on tritium retention is also evaluated for both cases. Thanks to the simulation, the evolutions of the tritium retention and the tritium migration depth are obtained as a function of the implanted flux and the number of cycles. From these evolutions, extrapolation laws are built to estimate the number of cycles needed for tritium to permeate from the implantation zone to the cooled surface and to quantify the corresponding retention of tritium throughout the W PFC.}, language = {en}, - urldate = {2021-06-25}, + urldate = {2019-10-07}, journal = {Physica Scripta}, - author = {Lasa, A. and Canik, J. M. and Blondel, S. and Younkin, T. R. and Curreli, D. and Drobny, J. and Roth, P. and Cianciosa, M. and Elwasif, W. and Green, D. L. and Wirth, B. D.}, - month = jan, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {014041}, - file = {Lasa et al. - 2020 - Multi-physics modeling of the long-term evolution .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WRQRYH85\\Lasa et al. - 2020 - Multi-physics modeling of the long-term evolution .pdf:application/pdf}, + author = {Hodille, E. A. and Bernard, E. and Markelj, S. and Mougenot, J. and Becquart, C. S. and Bisson, R. and Grisolia, C.}, + month = oct, + year = {2017}, + keywords = {Macroscopic rate equations}, + pages = {014033}, + file = {Hodille et al. - 2017 - Estimation of the tritium retention in ITER tungst.pdf:D\:\\Logiciels\\data_zotero\\storage\\KE2SBJ4Q\\Hodille et al. - 2017 - Estimation of the tritium retention in ITER tungst.pdf:application/pdf}, +} + +@article{de_temmerman_efficiency_2017, + series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, + title = {Efficiency of thermal outgassing for tritium retention measurement and removal in {ITER}}, + volume = {12}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179116301284}, + doi = {10.1016/j.nme.2016.10.016}, + abstract = {As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg. Simulations and extrapolations from existing experiments indicate that T-retention in ITER will mainly be driven by co-deposition with beryllium (Be) eroded from the first wall, with co-deposits forming mainly in the divertor region but also possibly on the first wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is being designed to locally measure the T-retention in co-deposits forming on the inner divertor baffle of ITER. Regarding tritium removal, the baseline strategy is to perform baking of the plasma-facing components, at 513K for the FW and 623K for the divertor. Both baking and laser desorption rely on the thermal desorption of tritium from the surface, the efficiency of which remains unclear for thick (and possibly impure) co-deposits. This contribution reports on the results of TMAP7 studies of this efficiency for ITER-relevant deposits.}, + urldate = {2019-10-07}, + journal = {Nuclear Materials and Energy}, + author = {De Temmerman, G. and Baldwin, M. J. and Anthoine, D. and Heinola, K. and Jan, A. and Jepu, I. and Likonen, J. and Lungu, C. P. and Porosnicu, C. and Pitts, R. A.}, + month = aug, + year = {2017}, + keywords = {Macroscopic rate equations}, + pages = {267--272}, + file = {De Temmerman et al. - 2017 - Efficiency of thermal outgassing for tritium reten.pdf:D\:\\Logiciels\\data_zotero\\storage\\CTQQUCCZ\\De Temmerman et al. - 2017 - Efficiency of thermal outgassing for tritium reten.pdf:application/pdf}, } -@article{kaveeva_solps-iter_2020, - title = {{SOLPS}-{ITER} modelling of {ITER} edge plasma with drifts and currents}, - volume = {60}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/ab73c1}, - doi = {10.1088/1741-4326/ab73c1}, - abstract = {Using the new version of the SOLPS plasma boundary code package, SOLPS-ITER, this paper presents the first ever simulations of the ITER burning baseline H-mode edge plasma with drifts and currents activated. Neon (Ne) seeded discharges for divertor power dissipation are considered. The results for divertor and scrape-off layer (SOL) parameters with and without drifts are compared, both for the SOLPS-ITER simulations and against the earlier SOLPS-4.3 modelling (which did not include a drift description) constituting the bulk of the existing ITER divertor simulation database. Whereas the drift effect on the equatorial midplane (main chamber) density and temperature profiles is moderate, drifts increase the peak heat flow to the outer divertor target. This effect is more pronounced for regimes with low sub-divertor neutral pressure, when even drift-free SOLPS4.3 simulations find strong out-in target power asymmetries. An important conclusion is thus that if ITER operates as expected with partially detached divertor targets, drifts should not influence the power handling, but that in the case of divertor reattachment, they will act to worsen the target loading, increasing the need for development of reliable schemes for detachment control. Comparing SOLPS-4.3 and SOLPS-ITER results for the key peak target heat flux versus sub-divertor neutral pressure operating domain, SOLPS-ITER with drifts predicts a narrower operational window for the divertor pressure.}, +@article{sun_critical_2014, + title = {Critical concentration for hydrogen bubble formation in metals}, + volume = {26}, + issn = {0953-8984}, + doi = {10.1088/0953-8984/26/39/395402}, + abstract = {Employing a thermodynamic model with previously calculated first-principle energetics as inputs, we determined the hydrogen (H) concentration at the interstitial and monovacancy as well as its dependence on temperature and pressure in tungsten and molybdenum. Based on this, we predicted the critical H concentration for H bubble formation at different temperatures. The critical concentration, defined as the value when the concentration of H at a certain mH-vacancy complex first became equal to that of H at the interstitial, was 24 ppm/7.3 GPa and 410 ppm/4.7 GPa at 600 K in tungsten and molybdenum in the case of a monovacancy. Beyond the critical H concentration, numerous H atoms accumulated in the monovacancy, leading to the formation and rapid growth of H-vacancy complexes, which was considered the preliminary stage of H bubble formation. We expect that the proposed approach will be generally used to determine the critical H concentration for H bubble formation in metals.}, language = {en}, - number = {4}, - urldate = {2021-06-21}, - journal = {Nuclear Fusion}, - author = {Kaveeva, E. and Rozhansky, V. and Senichenkov, I. and Sytova, E. and Veselova, I. and Voskoboynikov, S. and Bonnin, X. and Pitts, R. A. and Kukushkin, A. S. and Wiesen, S. and Coster, D.}, - month = mar, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {046019}, + number = {39}, + journal = {Journal of Physics: Condensed Matter}, + author = {Sun, Lu and Jin, Shuo and Zhou, Hong-Bo and Zhang, Ying and Zhang, Wenqing and Ueda, Y. and Lee, H. T. and Lu, Guang-Hong}, + month = sep, + year = {2014}, + keywords = {Density Functional Theory, Bubble}, + pages = {395402}, + file = {Sun et al. - 2014 - Critical concentration for hydrogen bubble formati.pdf:D\:\\Logiciels\\data_zotero\\storage\\MLA7WRM3\\Sun et al. - 2014 - Critical concentration for hydrogen bubble formati.pdf:application/pdf}, } -@article{park_assessment_2020, - title = {Assessment of {ITER} divertor performance during early operation phases}, - volume = {61}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/abc1ce}, - doi = {10.1088/1741-4326/abc1ce}, - abstract = {During the ITER design phase, the focus of ITER boundary plasma modeling activities has been on divertor performance under baseline H-mode, fusion power operation (FPO) conditions. However, early ITER operation will be primarily with hydrogen fuel in L-mode, in the pre-fusion power operation 1 (PFPO-1) phase. Here, the SOLPS-ITER code is used to evaluate divertor performance during this non-active phase. To verify the assumptions used in the existing high power simulation database, gas throughput scans were performed for two types of divertor surface material (beryllium and tungsten) and two gas puff locations (divertor and main chamber). The adoption of beryllium target surfaces simulates the effect of main chamber material erosion and migration and, along with main chamber gas injection, is the current default for the high power database. Depending on the divertor surface material, the atom to molecule ratio of the recycled neutral particles varies. This modifies the momentum and power loss mechanisms arising from plasma–neutral interactions. However, since the effect of atomic and molecular reactions are compensatory, the ‘total’ power and momentum losses are relatively insensitive to the target surface material. Similarly, the impact of gas puff location on divertor plasma parameters is not significant, though main chamber injection provides an additional ionization source in the upstream scrape-off layer (SOL) and leads to moderate changes in the upstream density and far SOL parameters. However, these effects can be neglected within the available range of the gas puff and pump rates in ITER. Since beryllium and tungsten are materials at both extremes in terms of surface reflection properties, the conclusions may be applicable to other divertor surface materials. An important additional finding of the study is that the insensitivity of upstream density to divertor neutral pressure found in the FPO database is also recovered in these PFPO-1 simulations.}, +@article{schmid_comparison_2012, + title = {Comparison of hydrogen retention in {W} and {W}/{Ta} alloys}, + volume = {426}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311512001730}, + doi = {10.1016/j.jnucmat.2012.04.003}, + abstract = {The extreme brittleness of tungsten (W) is one of the challenges of using W as first wall material. One attempt to alleviate this problem is to use W alloys with better mechanical properties. However these alloying elements must not degrade the favorable properties of W with respect to its application at the first wall of fusion devices: low sputter yield and hydrogen inventory. In this work we investigate the hydrogen retention in the recently proposed W/Ta alloys under deuterium ion bombardment. By directly comparing pure W and W/Ta alloys with 1\% and 5\% Ta content we found that the W/Ta alloys retain significantly more hydrogen than pure W under identical implantation conditions. Our finding of increased hydrogen retention together with the fact that the Ta alloying did not improve the brittleness makes W/Ta alloys an unacceptable choice for the first wall of fusion devices.}, language = {en}, number = {1}, - urldate = {2021-06-21}, - journal = {Nuclear Fusion}, - author = {Park, Jae-Sun and Bonnin, Xavier and Pitts, Richard}, - month = dec, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {016021}, -} - -@phdthesis{dolan_tritium_2021, - type = {Thesis}, - title = {Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor}, - copyright = {MIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided.}, - url = {https://dspace.mit.edu/handle/1721.1/131004}, - abstract = {Advanced reactor concepts which use a lithium- or beryllium-bearing primary salt coolant will require technical solutions to mitigate the environmental release of tritium. One such design is the Fluoride-Salt-Cooled High-Temperature Reactor (FHR), which combines a molten Flibe (2LiF-BeF₂) salt coolant and tri-structural isotropic coated-particle fuel to produce power or process heat. Compared to current water-cooled reactors, managing tritium release from a FHR is further complicated by the mobility of tritium at high temperatures and limited knowledge of interactions between tritium and nuclear graphite in the molten fluoride salt environment. The total activity, chemical forms, and retention mechanisms for tritium in nuclear graphite were studied through thermal desorption analysis of sample materials from three in-core Flibe salt irradiations (denoted FS-1, FS-2, and FS-3) at the MIT Reactor (MITR).}, - language = {eng}, - urldate = {2021-07-08}, - school = {Massachusetts Institute of Technology}, - author = {Dolan, Kieran Patrick}, - year = {2021}, - note = {Accepted: 2021-06-17T17:21:11Z}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NFSWCSCT\\Dolan - 2021 - Tritium retention in nuclear graphite, system-leve.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TXMLRMJM\\131004.html:text/html}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Schmid, K. and Rieger, V. and Manhard, A.}, + month = jul, + year = {2012}, + keywords = {Experiment}, + pages = {247--253}, + file = {Schmid et al. - 2012 - Comparison of hydrogen retention in W and WTa all.pdf:D\:\\Logiciels\\data_zotero\\storage\\5M529LGL\\Schmid et al. - 2012 - Comparison of hydrogen retention in W and WTa all.pdf:application/pdf}, } -@article{hecht_new_2012, - title = {New development in freefem++}, - volume = {20}, - issn = {1569-3953, 1570-2820}, - url = {https://www.degruyter.com/document/doi/10.1515/jnum-2012-0013/html}, - doi = {10.1515/jnum-2012-0013}, - abstract = {This is a short presentation to the capability of the freefem++ software, in section 1, we recall most of the characteristics of the software, In section 2, we recall how to to build a weak form form of an partial differential equation (PDE) from the strong form of the PDE. In three last sections, we present different problem, tools to illustrated the software. First we do mesh adaptation problem in two and three dimension,, secondly, we solve numerically a Phase change with Natural Convection, and the finally to show the HPC possibility we show a Schwarz Domain Decomposition problem on parallel computer.}, +@article{quiros_blister_2017, + series = {Proceedings of the 22nd {International} {Conference} on {Plasma} {Surface} {Interactions} 2016, 22nd {PSI}}, + title = {Blister formation and hydrogen retention in aluminium and beryllium: {A} modeling and experimental approach}, + volume = {12}, + issn = {2352-1791}, + shorttitle = {Blister formation and hydrogen retention in aluminium and beryllium}, + doi = {10.1016/j.nme.2016.12.036}, + abstract = {Experiments were performed in a low pressure-high density plasma reactor in order to study the impact of hydrogen retention in aluminium under plasma conditions. Microscopy scans of the surface were performed before and after 1h plasma exposure (fluence 6.1 ×1023ions/m2) where it is seen that blisters start to nucleate at the grain boundaries. Investigation on blister growth kinetics was performed for fluences ranging between 6 ×1023 and 3.7 ×1024ions/m2. The evolution of the characteristic size of the projected area was also analyzed. Finally, a macroscopic rate equations (MRE) code was used to simulate hydrogen retention and diffusion in Al and bubble growth in the bulk was simulated using experimental results. This model was also used to simulate these phenomena in Be and compare its behavior with respect to Al.}, language = {en}, - number = {3-4}, - urldate = {2021-07-14}, - journal = {Journal of Numerical Mathematics}, - author = {Hecht, F.}, - month = jan, - year = {2012}, - file = {Hecht - 2012 - New development in freefem++.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DLBP27YD\\Hecht - 2012 - New development in freefem++.pdf:application/pdf}, + journal = {Nuclear Materials and Energy}, + author = {Quirós, C. and Mougenot, J. and Lombardi, G. and Redolfi, M. and Brinza, O. and Charles, Y. and Michau, A. and Hassouni, K.}, + month = aug, + year = {2017}, + keywords = {Experiment, Macroscopic rate equations}, + pages = {1178--1183}, + file = {Quirós et al. - 2017 - Blister formation and hydrogen retention in alumin.pdf:D\:\\Logiciels\\data_zotero\\storage\\2FEKSEVD\\Quirós et al. - 2017 - Blister formation and hydrogen retention in alumin.pdf:application/pdf}, } -@article{arndt_dealii_2021, - series = {Development and {Application} of {Open}-source {Software} for {Problems} with {Numerical} {PDEs}}, - title = {The deal.{II} finite element library: {Design}, features, and insights}, - volume = {81}, - issn = {0898-1221}, - shorttitle = {The deal.{II} finite element library}, - url = {https://www.sciencedirect.com/science/article/pii/S0898122120300894}, - doi = {10.1016/j.camwa.2020.02.022}, - abstract = {deal.II is a state-of-the-art finite element library focused on generality, dimension-independent programming, parallelism, and extensibility. Herein, we outline its primary design considerations and its sophisticated features such as distributed meshes, hp-adaptivity, support for complex geometries, and matrix-free algorithms. But deal.II is more than just a software library: It is also a diverse and worldwide community of developers and users, as well as an educational platform. We therefore also discuss some of the technical and social challenges and lessons learned in running a large community software project over the course of two decades.}, +@article{lu_review_2014, + title = {A review of modelling and simulation of hydrogen behaviour in tungsten at different scales}, + volume = {54}, + issn = {0029-5515}, + doi = {10.1088/0029-5515/54/8/086001}, + abstract = {Tungsten (W) is considered to be one of the most promising plasma-facing materials (PFMs) for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely high fluxes of low-energy hydrogen (H) isotopes, leading to retention of H isotopes and blistering in W, which will degrade the thermal and mechanical properties of W. Modelling and simulation are indispensable to understand the behaviour of H isotopes including dissolution, diffusion, accumulation and bubble formation, which can contribute directly to the design, preparation and application of W as a PFM under a fusion environment. This paper reviews the recent findings regarding the behaviour of H in W obtained via modelling and simulation at different scales.}, language = {en}, - urldate = {2021-07-14}, - journal = {Computers \& Mathematics with Applications}, - author = {Arndt, Daniel and Bangerth, Wolfgang and Davydov, Denis and Heister, Timo and Heltai, Luca and Kronbichler, Martin and Maier, Matthias and Pelteret, Jean-Paul and Turcksin, Bruno and Wells, David}, - month = jan, - year = {2021}, - keywords = {Software design, Finite elements, Mathematical software, Scientific computing}, - pages = {407--422}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FB5JQUWY\\S0898122120300894.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XUMNAEXR\\Arndt et al. - 2021 - The deal.II finite element library Design, featur.pdf:application/pdf}, + number = {8}, + journal = {Nuclear Fusion}, + author = {Lu, Guang-Hong and Zhou, Hong-Bo and Becquart, Charlotte S.}, + month = jul, + year = {2014}, + keywords = {Density Functional Theory}, + pages = {086001}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Z7Y5TL4T\\Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:application/pdf;Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:D\:\\Logiciels\\data_zotero\\storage\\3ANYZCGN\\Lu et al. - 2014 - A review of modelling and simulation of hydrogen b.pdf:application/pdf}, } -@article{permann_moose_2020, - title = {{MOOSE}: {Enabling} massively parallel multiphysics simulation}, - volume = {11}, - issn = {2352-7110}, - shorttitle = {{MOOSE}}, - url = {https://www.sciencedirect.com/science/article/pii/S2352711019302973}, - doi = {10.1016/j.softx.2020.100430}, - abstract = {Harnessing modern parallel computing resources to achieve complex multiphysics simulations is a daunting task. The Multiphysics Object Oriented Simulation Environment (MOOSE) aims to enable such development by providing simplified interfaces for specification of partial differential equations, boundary conditions, material properties, and all aspects of a simulation without the need to consider the parallel, adaptive, nonlinear, finite element solve that is handled internally. Through the use of interfaces and inheritance, each portion of a simulation becomes reusable and composable in a manner that allows disparate research groups to share code and create an ecosystem of growing capability that lowers the barrier for the creation of multiphysics simulation codes. Included within the framework is a unique capability for building multiscale, multiphysics simulations through simultaneous execution of multiple sub-applications with data transfers between the scales. Other capabilities include automatic differentiation, scaling to a large number of processors, hybrid parallelism, and mesh adaptivity. To date, MOOSE-based applications have been created in areas of science and engineering such as nuclear physics, geothermal science, magneto-hydrodynamics, seismic events, compressible and incompressible fluid flow, microstructure evolution, and advanced manufacturing processes.}, +@article{zhang_hydrogen_2018, + series = {Special {Section} on "18th {International} {Conference} on {Fusion} {Reactor} {Materials}"}, + title = {Hydrogen diffusion behavior in tungsten under anisotropic strain}, + volume = {511}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311517317889}, + doi = {10.1016/j.jnucmat.2018.05.061}, + abstract = {In future fusion devices, the incident hydrogen plasma with high mobility can diffuse deep into tungsten bulk, which is directly relevant with hydrogen isotopes permeation and retention in tungsten. In this work, density functional theory (DFT) and object kinetic Monte Carlo (OKMC) simulations are adopted to investigate the hydrogen diffusion behavior in tungsten under anisotropic uniaxial strain from −2.5\% to 2.5\%. As presented by our DFT calculations, there are two types of hydrogen diffusion paths when applying strain, including one path perpendicular to the strain direction and another path largely along the strain direction. The migration energy barriers of these two paths have opposite variation tendencies in tensile or compressive condition. Our OKMC calculations based on DFT input show that, in tensile condition, the hydrogen diffusion is restrained despite the lower energy barrier of the corresponding diffusion path. In compressive condition, the hydrogen diffusion along the strain direction is enhanced, while that perpendicular to the strain direction is suppressed. The hydrogen diffusivity under anisotropic strain at the temperature range from 400 K to 1800 K is determined. It is demonstrated that tensile strain can suppress the diffusivity, while compressive strain can either suppress or facilitate the diffusivity depending on the temperature and the strain value. The anisotropic strain exhibits distinct effect on hydrogen diffusivity at lower temperature but its effect is minimal as the temperature increases.}, language = {en}, - urldate = {2021-07-14}, - journal = {SoftwareX}, - author = {Permann, Cody J. and Gaston, Derek R. and Andrš, David and Carlsen, Robert W. and Kong, Fande and Lindsay, Alexander D. and Miller, Jason M. and Peterson, John W. and Slaughter, Andrew E. and Stogner, Roy H. and Martineau, Richard C.}, - month = jan, - year = {2020}, - keywords = {Multiscale, Finite-element, Framework, Multiphysics, Parallel}, - pages = {100430}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UEBTI36N\\S2352711019302973.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FY3A5SV2\\Permann et al. - 2020 - MOOSE Enabling massively parallel multiphysics si.pdf:application/pdf}, + urldate = {2019-11-07}, + journal = {Journal of Nuclear Materials}, + author = {Zhang, Xuesong and Xu, Ke and Niu, Liang-Liang and Zhang, Ying and Lu, Guang-Hong}, + month = dec, + year = {2018}, + keywords = {Density Functional Theory, Monte Carlo}, + pages = {574--581}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\QS9LLHXK\\Zhang et al. - 2018 - Hydrogen diffusion behavior in tungsten under anis.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CGF9WRII\\S0022311517317889.html:text/html}, } -@misc{kolev_tzanio_modular_2010, - title = {Modular {Finite} {Element} {Methods} ({MFEM})}, - url = {https://www.osti.gov/doecode/biblio/35738}, - abstract = {MFEM is a modular parallel C++ library for finite element methods. Its goal is to enable high-performance scalable finite element discretization research and application development on a wide variety of platforms, ranging from laptops to supercomputers.}, - urldate = {2021-07-14}, - publisher = {Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)}, - author = {Kolev, Tzanio and Dobrev, Veselin}, - year = {2010}, - doi = {10.11578/DC.20171025.1248}, - note = {Language: en}, +@article{blondel_xolotl:_nodate, + title = {Xolotl: a cluster dynamics code to predict gas bubble evolution in solids}, + language = {en}, + author = {Blondel, Sophie and Lasa, Ane and Maroudas, Dimitrios and Roth, Philip C}, + keywords = {Cluster dynamics, Bubble}, + pages = {32}, + file = {Blondel et al. - Xolotl a cluster dynamics code to predict gas bub.pdf:D\:\\Logiciels\\data_zotero\\storage\\CXKFSHD7\\Blondel et al. - Xolotl a cluster dynamics code to predict gas bub.pdf:application/pdf}, } -@article{harris_array_2020, - title = {Array programming with {NumPy}}, - volume = {585}, - copyright = {2020 The Author(s)}, - issn = {1476-4687}, - url = {https://www.nature.com/articles/s41586-020-2649-2}, - doi = {10.1038/s41586-020-2649-2}, - abstract = {Array programming provides a powerful, compact and expressive syntax for accessing, manipulating and operating on data in vectors, matrices and higher-dimensional arrays. NumPy is the primary array programming library for the Python language. It has an essential role in research analysis pipelines in fields as diverse as physics, chemistry, astronomy, geoscience, biology, psychology, materials science, engineering, finance and economics. For example, in astronomy, NumPy was an important part of the software stack used in the discovery of gravitational waves1 and in the first imaging of a black hole2. Here we review how a few fundamental array concepts lead to a simple and powerful programming paradigm for organizing, exploring and analysing scientific data. NumPy is the foundation upon which the scientific Python ecosystem is constructed. It is so pervasive that several projects, targeting audiences with specialized needs, have developed their own NumPy-like interfaces and array objects. Owing to its central position in the ecosystem, NumPy increasingly acts as an interoperability layer between such array computation libraries and, together with its application programming interface (API), provides a flexible framework to support the next decade of scientific and industrial analysis.}, +@article{faney_spatially_2014, + title = {Spatially dependent cluster dynamics modeling of microstructure evolution in low energy helium irradiated tungsten}, + volume = {22}, + issn = {0965-0393}, + url = {https://iopscience.iop.org/article/10.1088/0965-0393/22/6/065010}, + doi = {10.1088/0965-0393/22/6/065010}, + abstract = {In fusion reactors, plasma facing components (PFC) and in particular the divertor will be irradiated with high fluxes of low energy (∼100 eV) helium and hydrogen ions. Tungsten is one of the leading candidate divertor materials for ITER and DEMO fusion reactors. However, the behavior of tungsten under high dose, coupled helium/hydrogen exposure remains to be fully understood. The PFC response and performance changes are intimately related to microstructural changes, such as the formation of point defect clusters, helium and hydrogen bubbles or dislocation loops. Computational materials modeling has been used to investigate the mechanisms controlling microstructural evolution in tungsten following high dose, high temperature helium exposure. The aim of this study is to understand and predict helium implantation, primary defect production and defect diffusion, helium-defect clustering and interactions below a tungsten surface exposed to low energy helium irradiation. The important defects include interstitial clusters, vacancy clusters, helium interstitials and helium-vacancy clusters. We report results from a one-dimensional, spatially dependent cluster dynamics model based on the continuum reaction–diffusion rate theory to describe the evolution in space and time of all these defects. The key parameter inputs to the model (diffusion coefficients, migration and binding energies, initial defect production) are determined from a combination of atomistic materials modeling and available experimental data.}, language = {en}, - number = {7825}, - urldate = {2021-07-13}, - journal = {Nature}, - author = {Harris, Charles R. and Millman, K. Jarrod and van der Walt, Stéfan J. and Gommers, Ralf and Virtanen, Pauli and Cournapeau, David and Wieser, Eric and Taylor, Julian and Berg, Sebastian and Smith, Nathaniel J. and Kern, Robert and Picus, Matti and Hoyer, Stephan and van Kerkwijk, Marten H. and Brett, Matthew and Haldane, Allan and del Río, Jaime Fernández and Wiebe, Mark and Peterson, Pearu and Gérard-Marchant, Pierre and Sheppard, Kevin and Reddy, Tyler and Weckesser, Warren and Abbasi, Hameer and Gohlke, Christoph and Oliphant, Travis E.}, - month = sep, - year = {2020}, - note = {Bandiera\_abtest: a -Cc\_license\_type: cc\_by -Cg\_type: Nature Research Journals -Number: 7825 -Primary\_atype: Reviews -Publisher: Nature Publishing Group -Subject\_term: Computational neuroscience;Computational science;Computer science;Software;Solar physics -Subject\_term\_id: computational-neuroscience;computational-science;computer-science;software;solar-physics}, - pages = {357--362}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YD8RZXXI\\s41586-020-2649-2.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4RM3MURH\\Harris et al. - 2020 - Array programming with NumPy.pdf:application/pdf}, + number = {6}, + urldate = {2019-10-28}, + journal = {Modelling and Simulation in Materials Science and Engineering}, + author = {Faney, T. and Wirth, B. D.}, + month = aug, + year = {2014}, + keywords = {Cluster dynamics, Bubble}, + pages = {065010}, + annote = { +1D modelling of He transport in W. +Cluster dynamics. +Many reactions are described. +Expressions for radii. +Implantation range calculated with SRIM. +Parameters (diffusivity, binding energies, capture radii) are determined with MD simulations. +TDS experiment reproduced at several fluences. +TDS peaks are due to dissociation of small clusters (4He.V -{\textgreater} 3He.V + He) +}, + file = {Faney et Wirth - 2014 - Spatially dependent cluster dynamics modeling of m.pdf:D\:\\Logiciels\\data_zotero\\storage\\PTWUZR2T\\Faney et Wirth - 2014 - Spatially dependent cluster dynamics modeling of m.pdf:application/pdf}, } -@article{schindelin_fiji_2012, - title = {Fiji: an open-source platform for biological-image analysis}, - volume = {9}, - copyright = {2012 Nature Publishing Group, a division of Macmillan Publishers Limited. All Rights Reserved.}, - issn = {1548-7105}, - shorttitle = {Fiji}, - url = {https://www.nature.com/articles/nmeth.2019}, - doi = {10.1038/nmeth.2019}, - abstract = {Presented is an overview of the image-analysis software platform Fiji, a distribution of ImageJ that updates the underlying ImageJ architecture and adds modern software design elements to expand the capabilities of the platform and facilitate collaboration between biologists and computer scientists.}, +@article{zhang_simulation_2019, + title = {Simulation of migration and coalescence of helium bubbles in nickel}, + volume = {518}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S002231151831434X}, + doi = {10.1016/j.jnucmat.2019.02.023}, + abstract = {The mechanism of migration and coalescence of nanoscale helium bubbles was studied using molecular dynamics. Small helium bubbles in nickel were observed to migrate in a random-walk style at temperatures higher than 0.7 Tm (melting point). Coalescence occurred when two helium bubbles approached each other, leading to the formation of a large bubble. The motion of the helium bubbles in nickel proceeds by displacement of nickel atoms on the surface, which causes the rearrangement of other nickel atoms, resulting surface diffusion. These findings indicate that migration and coalescence may be the possible growth mechanism for small helium bubbles in nickel at high temperature.}, language = {en}, - number = {7}, - urldate = {2021-07-13}, - journal = {Nature Methods}, - author = {Schindelin, Johannes and Arganda-Carreras, Ignacio and Frise, Erwin and Kaynig, Verena and Longair, Mark and Pietzsch, Tobias and Preibisch, Stephan and Rueden, Curtis and Saalfeld, Stephan and Schmid, Benjamin and Tinevez, Jean-Yves and White, Daniel James and Hartenstein, Volker and Eliceiri, Kevin and Tomancak, Pavel and Cardona, Albert}, - month = jul, - year = {2012}, - note = {Bandiera\_abtest: a -Cg\_type: Nature Research Journals -Number: 7 -Primary\_atype: Reviews -Publisher: Nature Publishing Group -Subject\_term: Imaging;Software -Subject\_term\_id: imaging;software}, - pages = {676--682}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CSF5JV63\\nmeth.html:text/html;Version acceptée:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2B3DHAN9\\Schindelin et al. - 2012 - Fiji an open-source platform for biological-image.pdf:application/pdf}, + urldate = {2019-10-28}, + journal = {Journal of Nuclear Materials}, + author = {Zhang, Wei and Han, Han and Dai, Jianxing and Ren, Cuilan and Wang, Chengbin and Yan, Long and Huang, Hefei and Zhu, Zhiyuan}, + month = may, + year = {2019}, + keywords = {Molecular Dynamics, Bubble}, + pages = {48--53}, + annote = { +This paper investigates the behaviour of bubbles in nickel. +The 2 different growth mechanisms are described (Ostwald ripening or migration/coalescence). +MD simulations are used to study evolution of helium bubbles. +Simulations show that migration speed is related to the size of the bubble (cluster) and temperature. +In this work, the pressure in the bubble at steady state is calculated from the volume, the number of atoms in the bubble, the temperature, and the virial stress based on forces in the region. +The coalescence of two bubbles (radius = 1nm) at a distance of 1.2 nm is simulated and bubbles move towards each other at a speed of 0.009 nm/ns at 1500K. +Coalescence also occurs at lower temperature but takes more time. +}, + file = {Zhang et al. - 2019 - Simulation of migration and coalescence of helium .pdf:D\:\\Logiciels\\data_zotero\\storage\\FRQTTC2L\\Zhang et al. - 2019 - Simulation of migration and coalescence of helium .pdf:application/pdf}, } -@article{1986STIN...8729795K, - title = {Finite-element reentry heat-transfer analysis of space shuttle {Orbiter}}, - volume = {87}, - url = {https://ui.adsabs.harvard.edu/abs/1986STIN...8729795K}, - abstract = {A structural performance and resizing (SPAR) finite-element thermal analysis computer program was used in the heat-transfer analysis of the space shuttle orbiter subjected to reentry aerodynamic heating. Three wing cross sections and one midfuselage cross section were selected for the thermal analysis. The predicted thermal protection system temperatures were found to agree well with flight-measured temperatures. The calculated aluminum structural temperatures also agreed reasonably well with the flight data from reentry to touchdown. The effects of internal radiation and of internal convection were found to be significant. The SPAR finite-element solutions agreed reasonably well with those obtained from the conventional finite-difference method.}, - urldate = {2021-08-19}, - journal = {NASA STI/Recon Technical Report N}, - author = {Ko, William L. and Quinn, Robert D. and Gong, Leslie}, - month = dec, - year = {1986}, - note = {ADS Bibcode: 1986STIN...8729795K}, - keywords = {Aluminum, Aerodynamic Heating, Aircraft Structures, Convection, Cross Sections, Finite Element Method, Fluid Mechanics and Heat Transfer, Heat Transfer Coefficients, Reentry Shielding, Space Shuttle Orbiters, Space Transportation System, Surface Temperature, Thermal Analysis, Thermal Protection, Wings}, - pages = {29795}, +@article{buzi_response_2017, + title = {Response of tungsten surfaces to helium and hydrogen plasma exposure under {ITER} relevant steady state and repetitive transient conditions}, + volume = {57}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/aa81e4}, + doi = {10.1088/1741-4326/aa81e4}, + abstract = {The effect of helium (He) plasma exposure, and associated surface modifications, on the thermal shock resistance of tungsten (W) under ITER relevant steady state and transient heat and particle loads was studied. W samples were exposed to steady state and pulsed He plasmas at surface base temperatures from 670 to 1170 K. The same exposures were repeated in hydrogen (H) to allow a direct comparison of the role of the ion species on the thermal shock resistance. Exposure to He plasma pulses caused the formation of fine cracking network on W samples which occurred at a higher density and smaller depths compared to H pulsed plasma irradiation. The peak temperature reached during an ELM-like plasma pulse increased by a factor 1.45 over the 100 s of He plasma exposure, indicating a deterioration of the thermal properties. Transient loading experiments were also performed using a high power pulsed laser during He plasma exposure, showing a significant modification of the target thermal response caused by the surface damage. The effect of He-induced morphology changes on the thermal response modification was found to be very small compared to that of transient-induced damage.}, + language = {en}, + number = {12}, + urldate = {2019-10-07}, + journal = {Nuclear Fusion}, + author = {Buzi, L. and Temmerman, G. De and Huisman, A. E. and Bardin, S. and Morgan, T. W. and Rasinski, M. and Pitts, R. A. and Oost, G. Van}, + month = sep, + year = {2017}, + keywords = {Experiment, Blistering}, + pages = {126009}, + file = {Buzi et al. - 2017 - Response of tungsten surfaces to helium and hydrog.pdf:D\:\\Logiciels\\data_zotero\\storage\\JJXGVR76\\Buzi et al. - 2017 - Response of tungsten surfaces to helium and hydrog.pdf:application/pdf}, } -@misc{kohn-seemann_alfkoehnfusion_plots_2021, - title = {alfkoehn/fusion\_plots: {Second} release of the fusion plot package (new plots added)}, - shorttitle = {alfkoehn/fusion\_plots}, - url = {https://zenodo.org/record/4946068}, - abstract = {The following plots have been added to the second release binding\_energy CMA\_diagram fusion\_cross\_section fusion\_reactivity plasma\_zoo}, - urldate = {2021-08-19}, - publisher = {Zenodo}, - author = {Köhn-Seemann, Alf and Hillairet, Julien}, - month = jun, - year = {2021}, - doi = {10.5281/zenodo.4946068}, - file = {Zenodo Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5H5FMU8A\\4946068.html:text/html;Zenodo Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2TNUBVHR\\4946068.html:text/html}, +@article{henriksson_molecular_2006, + title = {Molecular dynamics simulations of helium cluster formation in tungsten}, + volume = {244}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X05018288}, + doi = {10.1016/j.nimb.2005.10.020}, + abstract = {Molecular dynamics simulations of helium implantation into single-crystalline tungsten at 0 and 300K have been performed. Non-damaging ion energies of 50, 100 and 200eV were used. Clusters containing up to the order of 100 He atoms were formed. These clusters were nucleated athermally, via the creation of (111) crowdion interstitials and interstitial dislocation loop punching. Ruptures of He clusters were observed, but no associated ejection of W atoms.}, + language = {en}, + number = {2}, + urldate = {2019-10-30}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Henriksson, K. O. E. and Nordlund, K. and Keinonen, J.}, + month = mar, + year = {2006}, + keywords = {Tungsten, Helium, Molecular Dynamics, Bursting, Molecular dynamics simulations, Bubble, Implantation, (100) Surface, Cluster}, + pages = {377--391}, + file = {Henriksson et al. - 2006 - Molecular dynamics simulations of helium cluster f.pdf:D\:\\Logiciels\\data_zotero\\storage\\X2RTJVQL\\Henriksson et al. - 2006 - Molecular dynamics simulations of helium cluster f.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PEDJTZ93\\S0168583X05018288.html:text/html}, } -@article{ciraolo_first_2019, - title = {First modeling of strongly radiating {WEST} plasmas with {SOLEDGE}-{EIRENE}}, - volume = {20}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179118302461}, - doi = {10.1016/j.nme.2019.100685}, - abstract = {We present first results of SOLEDGE-EIRENE modeling a strongly radiating plasma in the WEST tokamak. Using measurements from a reciprocating Langmuir probe we have determined the SOLEDGE input parameters, i.e. separatrix density at outboard midplane and radial transport coefficients typical of L-mode plasma. We have performed deuterium plasma simulations with presence of oxygen, injected from the core boundary into the simulation domain. The comparison between the radiated power measured from the bolometry in the divertor region and the one computed from SOLEDGE simulations seems to indicate a concentration of oxygen of about 2\%. Moreover we have obtained good agreement between simulation results and experimental measurements on electron density and electron temperature profiles at the outer strike point. First qualitative analysis of spectroscopic synthetic diagnostic on Dα signals is also presented.}, +@article{hamid_molecular_2019, + title = {Molecular dynamics simulations of helium clustering and bubble growth under tungsten surfaces}, + volume = {163}, + issn = {0927-0256}, + url = {http://www.sciencedirect.com/science/article/pii/S0927025619301314}, + doi = {10.1016/j.commatsci.2019.03.008}, + abstract = {We study the surface response of W\{001\} to helium bombardment using molecular dynamics simulations. Simulations have been performed for incident helium of energy 80 eV and surface temperature 2100 K. The saturation of He retention has been observed to be high, a result of the bubbles trapping helium atoms and preventing them from diffusing to the surface and further back into the plasma. On the other hand, we have observe near-surface “cluster rupture” leading to the expulsion of helium atoms towards the vacuum. We have found that bubbles typically grow in a relatively narrow band of He/V ratios (1–3). Besides, it was observed that tungsten atoms migrated from the top surface into the bulk. The coalescence of helium bubbles has also been observed.}, language = {en}, - urldate = {2021-09-06}, - journal = {Nuclear Materials and Energy}, - author = {Ciraolo, G. and Thin, A. and Bufferand, H. and Bucalossi, J. and Fedorczak, N. and Gunn, J. P. and Pascal, J. Y. and Tamain, P. and Gil, C. and Gouin, A. and Meyer, O. and Devynck, P. and Vartanian, S. and Klepper, C. C. and Serre, E. and Nespoli, F. and Gallo, A. and Marandet, Y. and Rosato, J.}, - month = aug, + urldate = {2019-10-28}, + journal = {Computational Materials Science}, + author = {Hamid, Ali Y. and Sun, Jizhong and Zhang, Hongyu and Jadon, Arvind S. and Stirner, Thomas}, + month = jun, year = {2019}, - keywords = {Edge tokamak plasma, Fluid modeling, Transport}, - pages = {100685}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7JF7GXGF\\S2352179118302461.html:text/html}, + keywords = {Molecular Dynamics, Bubble}, + pages = {141--147}, + annote = { +MD simulations in W. +Investigation of W orientation. +Creation of He bubbles. +He bubbles prevent mobile He from diffusing back to the surface or deeper in the bulk. +He bubbles are observed along with coalescence and bursting events. +}, + file = {Hamid et al. - 2019 - Molecular dynamics simulations of helium clusterin.pdf:D\:\\Logiciels\\data_zotero\\storage\\XGXTWNTR\\Hamid et al. - 2019 - Molecular dynamics simulations of helium clusterin.pdf:application/pdf}, } -@article{juslin_molecular_2013, - series = {Proceedings of the 20th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion} {Devices}}, - title = {Molecular dynamics simulation of the effect of sub-surface helium bubbles on hydrogen retention in tungsten}, - volume = {438}, +@article{hu_interactions_2014, + title = {Interactions of mobile helium clusters with surfaces and grain boundaries of plasma-exposed tungsten}, + volume = {115}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.4874675}, + doi = {10.1063/1.4874675}, + abstract = {We report results of atomistic computations for the interactions of small mobile helium clusters (Hen) with free surfaces and grain boundaries (GBs) in tungsten toward development of continuum drift-diffusion-reaction models for the dynamics of mobile helium clusters in plasma-exposed tungsten. Molecular-statics (MS) simulations based on reliable many-body interatomic potentials are carried out for Hen (1 ≤ n ≤ 7) clusters near sinks to obtain the potential energy profiles of the Hen clusters as a function of the clusters' center-of-mass distance from a sink. Sinks investigated include surfaces, GBs, and regions in the vicinity of junctions where GBs intersect free surfaces. Elastic interaction potentials based on elastic inclusion theory provide an excellent description of the MS results for the cluster-sink interactions. The key parameter in the elastic models is the sink segregation strength, which is found to increase with increasing cluster size. Such cluster-sink interactions are responsible for the migration of small helium clusters by drift and for helium segregation on surfaces and grain boundaries in tungsten. Such helium segregation on sinks is observed in large-scale molecular-dynamics simulations of helium aggregation in model polycrystalline tungsten at 933 K upon helium implantation.}, + number = {17}, + urldate = {2019-10-31}, + journal = {Journal of Applied Physics}, + author = {Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, + month = may, + year = {2014}, + pages = {173512}, +} + +@article{woller_dynamic_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Dynamic measurement of the helium concentration of evolving tungsten nanostructures using {Elastic} {Recoil} {Detection} during plasma exposure}, + volume = {463}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S002231151300278X}, - doi = {10.1016/j.jnucmat.2013.01.270}, - abstract = {Nanometer-sized bubbles in tungsten containing various concentrations of helium and/or hydrogen gas were studied using molecular dynamics simulations. Bubbles of different sizes and compositions were relaxed and evolved at temperatures from 300K to 2100K. Helium atoms are evenly distributed inside the bubble at all temperatures, while the hydrogen tends to diffuse to the bubble periphery. In all cases a large amount of hydrogen is bound within the first 1–2 layers of the tungsten matrix surrounding the bubble, though clear dependencies on temperature and bubble composition were found.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514009337}, + doi = {10.1016/j.jnucmat.2014.11.126}, + abstract = {Helium (He) concentration depth profiles of evolving tungsten (W) nanostructures have been measured for the first time using in situ Elastic Recoil Detection (ERD) throughout plasma irradiation. Exposures resulting in fuzzy and non-fuzzy surfaces were analyzed in order to illuminate the role of He during the development of these surface morphologies. ERD was performed on samples with surface temperatures from Ts=530–1100K and irradiated by He flux densities of ΓHe∼1020–1022 m−2s−1. He concentration profiles in samples that developed either non-fuzzy or fuzzy surfaces are uniformly shaped with concentrations of 1.5–7at.\%, which is presumed to be too low for pressure driven growth models. Therefore, surface morphology changes are not perpetuated by continuous bubble bursting deformation. Also, a threshold in He flux density above 1020m−2s−1 is suggested by using in situ ERD to monitor the depth profile evolution of the He-rich layer while changing the flux during exposure.}, language = {en}, - urldate = {2021-09-06}, + urldate = {2019-11-04}, journal = {Journal of Nuclear Materials}, - author = {Juslin, N. and Wirth, B. D.}, - month = jul, - year = {2013}, - pages = {S1221--S1223}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TRUWS9E3\\S002231151300278X.html:text/html}, + author = {Woller, K. B. and Whyte, D. G. and Wright, G. M.}, + month = aug, + year = {2015}, + keywords = {Experiment, Fuzz}, + pages = {289--293}, + file = {Woller et al. - 2015 - Dynamic measurement of the helium concentration of.pdf:D\:\\Logiciels\\data_zotero\\storage\\MSD8287P\\Woller et al. - 2015 - Dynamic measurement of the helium concentration of.pdf:application/pdf}, } -@article{urgorri_influence_2021, - title = {The influence of {MHD} boundary layers on tritium permeation in {PbLi} flows for fusion breeding blankets}, - volume = {181}, - issn = {0017-9310}, - url = {https://www.sciencedirect.com/science/article/pii/S0017931021010115}, - doi = {10.1016/j.ijheatmasstransfer.2021.121906}, - abstract = {In PbLi based breeding blanket concepts, tritium is produced inside the liquid metal and drag out of the reactor by the liquid metal flow. However, undesired permeation through the channels and pipes walls occurs spontaneously since tritium naturally diffuses in the opposite direction of the concentration gradient. This way tritium can reach the blanket coolant circuit or even the exterior with an impact on the tritium self-sustainability and the safety of the plant. Similarly to heat transfer processes, permeation through the walls in the interface between the flow and the steel is mostly affected by the dynamics of the boundary layers. This is ruled by the electrical coupling between the moving conductor and the conducting walls as a result of the Magnetohydrodynamics (MHD) interactions which dominate the flow dynamics. In this work, the connection between the MHD forces and tritium transport is numerically studied using the simulation platform ANSYS-Fluent. The velocity profiles of a PbLi test channel have been firstly computed in a wide range of Hartmann numbers from 102 to 104. These velocity profiles are then applied to a 3D tritium transport model developed with the customization capabilities of the same platform. A series of tritium transport simulations are carried out considering different permeation regimes: surface-limited, diffusion-limited and intermediate regimes. The development of the concentration boundary layers along the channel is studied in different permeation regimes, magnetic fields and velocity fields. This has allowed correlating the Sherwood number (Sh) with the Hartmann (Ha), Reynolds (Re) and permeation numbers (W).}, +@article{lemahieu_h/he_2016, + series = {Proceedings of the 12th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-12 ({ISFNT}-12)}, + title = {H/{He} irradiation on tungsten exposed to {ELM}-like thermal shocks}, + volume = {109-111}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379616302319}, + doi = {10.1016/j.fusengdes.2016.03.035}, + abstract = {ELM-like thermal shocks and H/He particle exposure were subsequently applied on tungsten samples. Polished test specimens underwent in the JUDITH1 electron beam facility 100 transient thermal events with a duration of 1ms. The absorbed heat flux was 0.4GWm−2 and 1.5GWm−2, which is above the material's damage threshold. These experiments were done at room temperature and with the samples heated to 400°C base temperature. Depending on the loading conditions the test specimens have either a crack network or showed surface roughening. The samples were then loaded in the GLADIS facility at different surface temperatures with a mixed H/He beam with a flux of 3.7×1021m−2s−1. Post-mortem analysis showed that the roughened surface did not alter the H/He induced surface modifications. In contrast to that on the test specimens that exhibited crack formation, phenomena such as bubble creation along the crack edge, formation of a shallow layer of nano-structures covering the crack opening, and the emerging of a porous structure which partially fills the crack are observed.}, language = {en}, - urldate = {2021-09-07}, - journal = {International Journal of Heat and Mass Transfer}, - author = {Urgorri, F. R. and Moreno, C. and Fernández-Berceruelo, I. and Rapisarda, D.}, - month = dec, - year = {2021}, - keywords = {Tritium transport, Breeding blanket, Magnetohydrodynamics, Mass transfer}, - pages = {121906}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QRJ9KMNE\\S0017931021010115.html:text/html}, + urldate = {2019-11-04}, + journal = {Fusion Engineering and Design}, + author = {Lemahieu, Nathan and Balden, Martin and Elgeti, Stefan and Greuner, Henri and Linke, Jochen and Maier, Hans and Pintsuk, Gerald and Wirtz, Marius and Van Oost, Guido and Noterdaeme, Jean-Marie}, + month = nov, + year = {2016}, + keywords = {Experiment, Bubble, Fuzz}, + pages = {169--174}, + file = {Lemahieu et al. - 2016 - HHe irradiation on tungsten exposed to ELM-like t.pdf:D\:\\Logiciels\\data_zotero\\storage\\D3M39Z9C\\Lemahieu et al. - 2016 - HHe irradiation on tungsten exposed to ELM-like t.pdf:application/pdf}, } -@article{noauthor_thermal_nodate, - title = {Thermal damage of tungsten-armored plasma-facing components under high heat flux loads}, +@article{markelj_hydrogen_2017, + title = {Hydrogen isotope accumulation in the helium implantation zone in tungsten}, + volume = {57}, + issn = {0029-5515}, + doi = {10.1088/1741-4326/aa6b27}, + abstract = {The influence of helium (He) on deuterium (D) transport and retention was studied experimentally in tungsten (W). Helium was implanted 1 µm deep into W to a maximum calculated concentration of 3.4 at.\%. To minimize the influence of displacement damage created during the He implantation on D retention, so-called self-damaged W was used. W was damaged by 20 MeV W ion bombardment and defects were populated by low-temperature D plasma at room temperature before He implantation. Deuterium depth profiling was performed in situ during isochronal annealing in the temperature range from 300 K to 800 K. It is shown for the first time unambiguously that He attracts D and locally increases D trapping. Deuterium retention increased by a factor of two as compared to a non-He implanted W reference after sample annealing at 450 K. Rate equation modelling can explain the measured D depth profiles quantitatively when keeping the de-trapping parameters unchanged but only increasing the number of traps in the He zone. This bolsters the confidence in the theoretical calculations predicting that more hydrogen isotopes can be stored around a He cluster zone.}, language = {en}, - pages = {10}, - file = {Thermal damage of tungsten-armored plasma-facing c.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\K7XMJP3U\\Thermal damage of tungsten-armored plasma-facing c.pdf:application/pdf}, + number = {6}, + journal = {Nuclear Fusion}, + author = {Markelj, S. and Schwarz-Selinger, T. and Založnik, A.}, + month = apr, + year = {2017}, + keywords = {Experiment, Macroscopic rate equations}, + pages = {064002}, + file = {Markelj et al. - 2017 - Hydrogen isotope accumulation in the helium implan.pdf:D\:\\Logiciels\\data_zotero\\storage\\3HY5B9GZ\\Markelj et al. - 2017 - Hydrogen isotope accumulation in the helium implan.pdf:application/pdf}, } -@article{fausser_tokamak_2012, - series = {Tenth {International} {Symposium} on {Fusion} {Nuclear} {Technology} ({ISFNT}-10)}, - title = {Tokamak {D}-{T} neutron source models for different plasma physics confinement modes}, - volume = {87}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379612000853}, - doi = {10.1016/j.fusengdes.2012.02.025}, - abstract = {Neutronic studies of European demonstration fusion power plant (DEMO) have been so far based on plasma physics low confinement mode (L-mode). Future tokamaks, nevertheless, may likely use alternative confinement modes such as high or advanced confinement modes (H\&A-mode). Based on analytical formulae used in plasma physics, H\&A-modes D-T neutron sources formulae are proposed in this paper. For that purpose, a tokamak random neutron source generator, TRANSGEN, has been built generating bidimensional (radial and poloidal) neutron source maps to be used as input for neutronics Monte-Carlo codes (TRIPOLI-4 and MCNP5). The impact of such a source on the neutronic behavior of the European DEMO-2007 Helium-cooled lithium–lead reactor concept has been assessed and compared with previous results obtained using a L-mode neutron source. An A-mode neutron source map from TRANSGEN has been used with the code TRIPOLI-4. Assuming the same fusion power, results show that main reactor global neutronic parameters, e.g. tritium breeding ratio and neutron multiplication factor, evolved slightly when compared to present uncertainties margin. However, local parameters, such as the neutron wall loading (NWL), change significantly compared to L-mode shape: from −22\% to +11\% for NWL.}, +@article{miyamoto_systematic_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Systematic investigation of the formation behavior of helium bubbles in tungsten}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514009131}, + doi = {10.1016/j.jnucmat.2014.10.098}, + abstract = {The formation of He bubbles in tungsten under exposure to a He plasma was systematically investigated using low energy (∼50eV) He+ ions with a wide fluence range (∼1023 to 1026m−2) in the linear divertor plasma simulator PISCES-A at several temperatures (523–973K). TEM observations after thinning exposed W samples with FIB revealed that the layer thickness ({\textgreater}30nm) of He bubbles largely exceeds the ion implantation range of a few nm. The size of He bubbles was found to increase with an increase in the sample temperature: it was around 10nm at 973K, while only small He bubbles of 1–2nm were observed at {\textless}773K. In addition, to obtain information on the initial formation behavior, in-situ TEM observations during He ion irradiation were also performed.}, language = {en}, - number = {5}, - urldate = {2021-09-21}, - journal = {Fusion Engineering and Design}, - author = {Fausser, Clement and Puma, Antonella Li and Gabriel, Franck and Villari, Rosaria}, + urldate = {2019-10-25}, + journal = {Journal of Nuclear Materials}, + author = {Miyamoto, M. and Mikami, S. and Nagashima, H. and Iijima, N. and Nishijima, D. and Doerner, R. P. and Yoshida, N. and Watanabe, H. and Ueda, Y. and Sagara, A.}, month = aug, - year = {2012}, - keywords = {DEMO, Neutronics, Plasma source description, TRIPOLI-4}, - pages = {787--792}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ARCDKAPY\\S0920379612000853.html:text/html}, + year = {2015}, + keywords = {Experiment, Bubble}, + pages = {333--336}, + annote = { +This paper is an experimental work and investigates He bubble formation under low energy (50 eV) He plasma exposure. +It was found that the size of the He bubbles increase with increasing sample temperature (10 nm-wide at 973K vs 1-2 nm-wide at temperatures below 773K). +Experimental parameters are given which could provide data for future simulations. +SEM and TEM images are given. +3 different temperatures (523K - 973K) of implantation and up to 6 different fluences (10{\textasciicircum}23 - 10{\textasciicircum}26 m{\textasciicircum}-2)  for each. +In addition, irradiation is made with 3 keV He+ ions at constant temperatures and increasing the helium fluence. +An overall mapping of the morphology based on temperature and fluence is given. +Quantitative comparison of bubble diameters and densities is given for different fluences. +At high temperature and high fluence, bubble density starts to decrease meaning a coalescence of the latter. +}, + file = {Miyamoto et al. - 2015 - Systematic investigation of the formation behavior.pdf:D\:\\Logiciels\\data_zotero\\storage\\A2NYSRF4\\Miyamoto et al. - 2015 - Systematic investigation of the formation behavior.pdf:application/pdf}, } -@article{bergstrom_mobility_2021, - title = {The mobility of small, over-pressurized helium bubbles in tungsten at 2000 {K}}, +@article{nishijima_sputtering_2011, + series = {Proceedings of the 19th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion}}, + title = {Sputtering properties of tungsten ‘fuzzy’ surfaces}, + volume = {415}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311521005298}, - doi = {10.1016/j.jnucmat.2021.153306}, - abstract = {Fusion reactor environments inevitably lead to the formation of high-pressure helium bubbles whose nucleation, growth, and diffusion strongly impact the performance of plasma-facing components. This research describes a diffusion mechanism of over-pressurized bubbles via a sequence of Frenkel pair nucleation, self-interstitial migration, and Frenkel pair annihilation. Molecular dynamics was used to simulate the diffusion of small bubbles in tungsten at 2000 K with helium-per-vacancy ratios in the range of 4.5 to 7. The diffusion coefficients are calculated and their dependence on helium content, number of vacancies, and number of attached self-interstitials is characterized. It is found that bubbles are most mobile when the nucleation/annihilation rates of Frenkel pairs are nearly equal and when the bubbles nucleate and annihilate a single self-interstitial. All bubbles experience a peak diffusivity, which can be as high as 10−11 m2/s decreasing with bubble size. The calculated diffusion coefficients provide valuable insight into the mobility of small, high-pressure bubbles, and can be used as input parameters in mesoscale models to improve predictions of plasma-surface interactions. (LA-UR-21-21881)}, + url = {http://www.sciencedirect.com/science/article/pii/S002231151000838X}, + doi = {10.1016/j.jnucmat.2010.12.017}, + abstract = {Sputtering yields of He-induced W ‘fuzzy’ surfaces bombarded by Ar have been measured in the linear divertor plasma simulator PISCES-B. It is found that the sputtering yield of a fuzzy surface, Yfuzzy, decreases with increasing fuzzy layer thickness, L, and saturates at ∼10\% of that of a smooth surface, Ysmooth, at L{\textgreater}1μm. The reduction in the sputtering yield is suspected to be due mainly to the porous structure of fuzz, since the ratio, Yfuzzy/Ysmooth follows (1−pfuzz), where pfuzz is the fuzz porosity. Further, Yfuzzy/Ysmooth is observed to increase with incident ion energy, Ei. This may be explained by an energy dependent change in the angular distribution of sputtered W atoms, since at lower Ei, the angular distribution is observed to become more butterfly-shaped. That is, a larger fraction of sputtered W atoms can line-of-sight deposit/stick onto neighboring fuzz nanostructures for lower Ei butterfly distributions, resulting in lower ratio of Yfuzzy/Ysmooth.}, language = {en}, - urldate = {2021-09-28}, + number = {1, Supplement}, + urldate = {2019-11-04}, journal = {Journal of Nuclear Materials}, - author = {Bergstrom, Z. J. and Perez, D. and Martínez, E.}, - month = sep, - year = {2021}, - keywords = {Helium, Tungsten, Diffusion, Bubbles}, - pages = {153306}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U7Q6AYE5\\S0022311521005298.html:text/html}, + author = {Nishijima, D. and Baldwin, M. J. and Doerner, R. P. and Yu, J. H.}, + month = aug, + year = {2011}, + keywords = {Experiment, Fuzz}, + pages = {S96--S99}, + file = {Nishijima et al. - 2011 - Sputtering properties of tungsten ‘fuzzy’ surfaces.pdf:D\:\\Logiciels\\data_zotero\\storage\\STJ448CU\\Nishijima et al. - 2011 - Sputtering properties of tungsten ‘fuzzy’ surfaces.pdf:application/pdf}, } -@article{hodille_modelling_2021-1, - title = {Modelling of hydrogen isotopes trapping, diffusion and permeation in divertor monoblocks under {ITER}-like conditions}, - copyright = {All rights reserved}, +@article{baldwin_helium_2008, + title = {Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions}, + volume = {48}, issn = {0029-5515}, - url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac2abc}, - doi = {10.1088/1741-4326/ac2abc}, - abstract = {In this work, the deuterium (D) retention in plasma facing components of the divertor of ITER is estimated. Three scenarios are simulated with 3 different surface temperatures, 1456 K, 870 K and 435 K. They represent the exposure of different parts of the divertor during an attached plasma. Our 1D rate equation model MHIMS (migration of hydrogen isotopes in materials) is used to model the retention in the super-saturated layer formed in the first 10 nm: the D retention integrated in this 10-nm layer is 1e19 Dm-2 for the coldest scenarios. It is also used to differentiate the evolution of deuterium retention during pulsed and continuous plasma exposure which shows that: (i) there is a retention during the ramp-down in the first 10 µm which is released during the ramp-up and (ii) the bulk retention is not affected by the cycling of plasma exposure. The concentration of mobile deuterium in the implantation zone is used as an input of our finite element code FESTIM which is used to assess the deuterium retention and migration in the 2D complex geometry of the actively cooled plasma facing components. In the end, this work enable to determine the three following macroscopic quantities: the total deuterium retention, the permeation flux to the cooling pipe and the desorption flux from the toroidal edges of the components. It is shown that (i) the coldest scenario leads to the highest retention despite the lowest exposure flux which has already been observed in past retention studies, (ii) the permeation to the cooling pipes happens after few thousands of seconds only for the hottest scenario, (iii) the release of deuterium from the toroidal edges is a small fuel recycling source.}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/48/3/035001}, + doi = {10.1088/0029-5515/48/3/035001}, + abstract = {Polished W discs exposed to pure He plasma in the PISCES-B linear-divertor-plasma simulator at 1120 and 1320 K are found to develop deeply nanostructured surface layers consisting of a conglomerate of amorphous ‘nanorods’. The growth of the thickness of the nanostructured layer is explored for exposure times spanning 300–(2.2 × 104) s in He plasmas of density ne ∼ 4 × 1018 m−3 and temperature Te ∼ 6–8 eV where the average He-ion surface-impact energy is ∼60 eV, below the threshold for physical sputtering. A nanostructured layer in excess of 5 µm thick is observed for the longest exposure time explored. The kinetics of the layer growth are found to follow Fick's law, characterized by an effective diffusive mechanism with coefficients of diffusion: D1120 K = 6.6 ± 0.4 × 10−12 cm2 s−1 and D1320 K = 2.0± 0.5 × 10−11 cm2 s−1. The diffusion of He atoms in W is considered too rapid to explain the observed growth of surface modification and points to the interplay of other mechanisms, such as the availability of thermal vacancies and/or the slower diffusion of He through the forming nanostructured layer.}, language = {en}, - urldate = {2021-10-04}, + number = {3}, + urldate = {2019-10-30}, journal = {Nuclear Fusion}, - author = {Hodille, Etienne Augustin and Delaporte-Mathurin, Rémi and Denis, Julien and Pečovnik, Matic and Bernard, Elodie and Ferro, Yves and Sakamoto, Ryuichi and Charles, Yann and Mougenot, Jonathan and De Backer, Andree and Becquart, Charlotte S and Markelj, Sabina and Grisolia, Christian}, - year = {2021}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RG7VVKUX\\Hodille et al. - 2021 - Modelling of hydrogen isotopes trapping, diffusion.pdf:application/pdf}, -} - -@misc{noauthor_permeation_nodate, - title = {Permeation and trapping of hydrogen in {Eurofer97} - {ScienceDirect}}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121001290?via%3Dihub}, - urldate = {2021-10-07}, - file = {Permeation and trapping of hydrogen in Eurofer97 - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I34P7J9H\\S2352179121001290.html:text/html}, -} - -@phdthesis{benannoune_simulations_2020, - type = {phdthesis}, - title = {Simulations {EF} du couplage entre diffusion et piégeage de l’hydrogène sous sollicitations thermomécaniques : {Applications} relatives au fer et au tungstène}, - shorttitle = {Simulations {EF} du couplage entre diffusion et piégeage de l’hydrogène sous sollicitations thermomécaniques}, - url = {https://tel.archives-ouvertes.fr/tel-03167860}, - abstract = {L‟objectif de ce travail de thèse est de reprendre les travaux précédents sur le couplage diffusion / plasticité sous Abaqus et d‟implémenter dans le code éléments finis un processus de piégeage transitoire dans une procédure utilisateur UMATHT, l‟équation de la chaleur dans une procédure UEL, et de modifier le comportement mécanique dans la procédure UMAT, afin de résoudre de manière couplée et simultanée les problèmes de diffusion/piégeage de l‟hydrogène soumis à des chargements thermomécaniques.Le modèle ainsi développé avec un couplage diffusion/piégeage transitoire a été confronté dans un premier temps, et validé sur plusieurs matériaux (tungstène et fer) par des comparaisons sur des cas tests avec d‟autres codes de la littérature (notamment le code MRE HIIPC). Puis, en considérant les variations des champs thermiques, l‟outil et l‟implémentation ont été validées sur des résultats expérimentaux de TDS sur du tungstène ainsi que sur d‟autres codes de la littérature sur le fer.Enfin, le modèle entièrement couplé a ainsi été utilisé sur des applications de chargements thermiques complexes sur une composante du futur tokamak d‟ITER (DFW). Les simulations 3D sur cette structure ont mis en évidence les effets de géométrie qui ne peuvent être pris en compte dans des simulations 1D. Elles ont permis de mettre également en exergue le rôle de la pression hydrostatique, la prise en compte de la dilatation thermique pouvant induire des écarts importants sur les résultats.}, - language = {fr}, - urldate = {2021-10-12}, - school = {Université Paris-Nord - Paris XIII}, - author = {Benannoune, Sofiane}, + author = {Baldwin, M. J. and Doerner, R. P.}, month = jan, - year = {2020}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YHLDLPKY\\tel-03167860.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3LW8DVYD\\Benannoune - 2020 - Simulations EF du couplage entre diffusion et piég.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ELLJWPT5\\tel-03167860.html:text/html}, + year = {2008}, + keywords = {Experiment, Fuzz}, + pages = {035001}, + file = {Baldwin et Doerner - 2008 - Helium induced nanoscopic morphology on tungsten u.pdf:D\:\\Logiciels\\data_zotero\\storage\\FJEPVE75\\Baldwin et Doerner - 2008 - Helium induced nanoscopic morphology on tungsten u.pdf:application/pdf}, +} + +@article{takamura_formation_2006, + title = {Formation of {Nanostructured} {Tungsten} with {Arborescent} {Shape} due to {Helium} {Plasma} {Irradiation}}, + volume = {1}, + doi = {10.1585/pfr.1.051}, + abstract = {Deeply nanostructured tungsten with an arborescent shape was found for the first time to be formed on tungsten-coated graphite by a high-flux helium plasma irradiation at surface temperatures of 1250 and 1600 K, an incident ion energy of 12 eV (well below the physical sputtering threshold) and a helium ion fluence of 3.5 × 1027 m-2.}, + journal = {Plasma and Fusion Research}, + author = {Takamura, Shuichi and Ohno, Noriyasu and Nishijima, Dai and Kajita, Shin}, + year = {2006}, + keywords = {Experiment, Fuzz}, + pages = {051--051}, + file = {Takamura et al. - 2006 - Formation of Nanostructured Tungsten with Arboresc.pdf:D\:\\Logiciels\\data_zotero\\storage\\SP9UEUI4\\Takamura et al. - 2006 - Formation of Nanostructured Tungsten with Arboresc.pdf:application/pdf}, } -@article{noauthor_pre-conceptual_2021, - title = {Pre-conceptual design of an encapsulated breeder commercial blanket for the {STEP} fusion reactor}, - volume = {172}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/abs/pii/S0920379621006852}, - doi = {10.1016/j.fusengdes.2021.112909}, - abstract = {As part of the UKAEA Spherical Tokamak for Energy Production (STEP) fusion power station programme, a novel breeding blanket design was assessed. A co…}, +@article{baldwin_formation_2010, + title = {Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades}, + volume = {404}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311510002849}, + doi = {10.1016/j.jnucmat.2010.06.034}, + abstract = {The response of a variety of W material grades to nanostructure ‘fuzz’ formation is explored. W targets are exposed to He or D2–0.2He plasmas in PISCES-B at 900–1320K to below sputter threshold He+ ions of energy 25–60eV for up to 2.2×104s. SEM and XPS reveal nanoscopic reorganization of the W surface to a layer of ‘fuzz’ of porosity ∼90\% as determined by a ‘fuzz’ removal/weight loss method. The variability of ‘fuzz’ growth is examined at 1120K for 1h durations: SR, SC and doped W grades – La2O3 (1\% wt.), Re (5\% and 10\% wt.), and TiC (1.5\% wt.) developed 2–3μm thick ‘fuzz’ layers, while a VPS grade developed a layer 4μm thick. An RC grade revealed additional ‘fuzz’ at deep ({\textgreater}100μm) grain boundaries. However, heat treatment up to 1900K produced reintegration of ‘fuzz’ with the bulk and He release at ∼1000K and ∼1400–1800K due to depopulation from vacancy complexes.}, language = {en}, - urldate = {2021-10-26}, - journal = {Fusion Engineering and Design}, - month = nov, - year = {2021}, - note = {Publisher: North-Holland}, - pages = {112909}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NFPY3RNG\\S0920379621006852.html:text/html}, + number = {3}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Baldwin, M. J. and Doerner, R. P.}, + month = sep, + year = {2010}, + keywords = {Experiment, Fuzz}, + pages = {165--173}, + file = {Baldwin et Doerner - 2010 - Formation of helium induced nanostructure ‘fuzz’ o.pdf:D\:\\Logiciels\\data_zotero\\storage\\X84YDP2C\\Baldwin et Doerner - 2010 - Formation of helium induced nanostructure ‘fuzz’ o.pdf:application/pdf}, } -@incollection{kirby_finite_2012, - address = {Berlin, Heidelberg}, - series = {Lecture {Notes} in {Computational} {Science} and {Engineering}}, - title = {The finite element method}, - isbn = {978-3-642-23099-8}, - url = {https://doi.org/10.1007/978-3-642-23099-8_2}, - abstract = {The finite element method has emerged as a universal method for the solution of differential equations. Much of the success of the finite element method can be attributed to its generality and elegance, allowing a wide range of differential equations from all areas of science to be analyzed and solved within a common framework. Another contributing factor to the success of the finite element method is the flexibility of formulation, allowing the properties of the discretization to be controlled by the choice of approximating finite element spaces.}, +@article{wright_tungsten_2012, + title = {Tungsten nano-tendril growth in the {Alcator} {C}-{Mod} divertor}, + volume = {52}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/52/4/042003}, + doi = {10.1088/0029-5515/52/4/042003}, + abstract = {Growth of tungsten nano-tendrils (‘fuzz’) has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14 consecutive helium L-mode discharges in Alcator C-Mod, the tip of a tungsten Langmuir probe at the outer strike point was fully covered with a layer of nano-tendrils. The thickness of the individual nano-tendrils (50–100 nm) and the depth of the layer (600 ± 150 nm) are consistent with observations from experiments on linear plasma devices. The observation of tungsten fuzz in a tokamak may have important implications for material erosion, dust formation, divertor lifetime and tokamak operations in next-step devices.}, language = {en}, - urldate = {2021-10-14}, - booktitle = {Automated {Solution} of {Differential} {Equations} by the {Finite} {Element} {Method}: {The} {FEniCS} {Book}}, - publisher = {Springer}, - author = {Kirby, Robert C. and Logg, Anders}, - editor = {Logg, Anders and Mardal, Kent-Andre and Wells, Garth}, + number = {4}, + urldate = {2019-10-30}, + journal = {Nuclear Fusion}, + author = {Wright, G. M. and Brunner, D. and Baldwin, M. J. and Doerner, R. P. and Labombard, B. and Lipschultz, B. and Terry, J. L. and Whyte, D. G.}, + month = mar, year = {2012}, - doi = {10.1007/978-3-642-23099-8_2}, - keywords = {Bilinear Form, Nodal Basis, Posteriori Error Estimate, Test Space, Variational Problem}, - pages = {77--94}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z5K7BUDI\\Kirby et Logg - 2012 - The finite element method.pdf:application/pdf}, + keywords = {Experiment, Fuzz}, + pages = {042003}, + file = {Wright et al. - 2012 - Tungsten nano-tendril growth in the Alcator C-Mod .pdf:D\:\\Logiciels\\data_zotero\\storage\\ZCEK7C3P\\Wright et al. - 2012 - Tungsten nano-tendril growth in the Alcator C-Mod .pdf:application/pdf}, } -@article{lasa_integrated_2021, - title = {Integrated model predictions on the impact of substrate damage on gas dynamics during {ITER} burning-plasma operations}, - volume = {61}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/ac2875}, - doi = {10.1088/1741-4326/ac2875}, - abstract = {Divertor design and choice of plasma-facing materials (PFM) will be essential to the success of next-generation fusion reactors as they operate under more powerful scenarios. Understanding and controlling interactions between the plasma and PFM is essential to making these choices. Within these plasma–material interactions and especially in tungsten (W), the interplay between the most abundant plasma species (hydrogen isotopes and helium, He) with the wall material alters fuel retention. However, this interplay is yet to be sufficiently understood to confidently project fuel retention levels to future fusion devices. The paper presents a series of integrated simulations of fusion plasmas and their interaction with tungsten. Specifically, this study assesses the impact of He plasma pre-exposure on hydrogenic species retention during 100 s of burning plasma operations (BPO) in ITER. Multiple pre-exposure scenarios are considered, including sub-surface damage resulting from exposures in the linear device PISCES and from early ITER He-operation. The predictions from these consecutive He-BPO exposures show that fuel content and spatial distribution in the material are largely determined by the He-induced damage, as manifest in: (i) changes in surface temperature expected during BPO have little effect on fuel retention in the presence of He-induced damage; (ii) gas content stabilizes quickly in substrates pre-exposed in PISCES, at levels set by the concentration of pre-existing vacancies, while it continues to increase in substrates initially pristine or pre-exposed to ITER He plasmas; (iii) the presence of He and He–V clusters in the near-surface region locally increases hydrogenic retention, but decreases its permeation; this results in hydrogenic species that remain closer to the surface in pre-damaged substrates, while the bulk content is higher for initially pristine cases. In summary, the interaction and binding of D and T with the pre-existing He–V clusters modifies retention and permeation of hydrogen species during ITER BPO.}, - language = {en}, - number = {11}, - urldate = {2021-11-15}, - author = {Lasa, A. and Blondel, S. and Bernholdt, D. E. and Canik, J. M. and Cianciosa, M. and Elwasif, W. R. and Green, D. L. and Roth, P. C. and Younkin, T. R. and Curreli, D. and Drobny, J. and Wirth, B. D.}, - month = oct, - year = {2021}, - note = {Publisher: IOP Publishing}, - pages = {116051}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JRQERAH6\\Lasa et al. - 2021 - Integrated model predictions on the impact of subs.pdf:application/pdf}, +@article{qin_helium_2019, + title = {Helium bubble nucleation at grain boundaries and its influence on intergranular fracture}, + volume = {99}, + issn = {1478-6435}, + url = {https://doi.org/10.1080/14786435.2018.1551634}, + doi = {10.1080/14786435.2018.1551634}, + abstract = {An in-depth understanding of the formation of intergranular helium bubbles and its relation to embrittlement is an important issue in the nuclear industry. In this paper, a thermodynamic model is developed to analyze the nucleation of intergranular helium bubbles. Microstructural observation using scanning electron microscopy and electron backscatter diffraction gives a detailed description for the relation between the bubble formation and the grain-boundary (GB) misorientation in helium-implanted nickel and Inconel X750. The theoretical and the experimental results confirm that the nucleation of intergranular helium bubbles is GB structure-dependent, the helium-to-vacancy ratio plays an important role in the bubble precipitation, and the interfacial tension of bubbles cannot be approximated to be the interfacial energy. The bubble-induced intergranular embrittlement in a polycrystal is modelled. The GB misorientation distribution, the intergranular bubble nucleation and growth and the GB connectivity are the key factors affecting the GB fracture toughness. The hoop ductility of the cladding tubes containing helium is analyzed. The hoop stress-induced increase in the GB energy promotes the precipitation of bubbles at the radial GBs and lead to the loss of tube ductility. Based on this work, the complicated correlation among the intergranular helium bubbles, the GB structure, the helium concentration, the applied stress and the helium embrittlement is clarified.}, + number = {6}, + urldate = {2019-10-31}, + journal = {Philosophical Magazine}, + author = {Qin, W. and Chauhan, A. K. and Szpunar, J. A.}, + month = mar, + year = {2019}, + keywords = {Experiment, Bubble}, + pages = {679--698}, } -@article{delaporte-mathurin_influence_2021-1, - title = {Influence of exposure conditions on helium transport and bubble growth in tungsten}, - volume = {11}, - copyright = {2021 The Author(s)}, - issn = {2045-2322}, - url = {https://www.nature.com/articles/s41598-021-93542-9}, - doi = {10.1038/s41598-021-93542-9}, - abstract = {Helium diffusion, clustering and bubble nucleation and growth is modelled using the finite element method. The existing model from Faney et al. (Model Simul Mater Sci Eng 22:065010, 2018; Nucl Fusion 55:013014, 2015) is implemented with FEniCS and simplified in order to greatly reduce the number of equations. A parametric study is performed to investigate the influence of exposure conditions on helium inventory, bubbles density and size. Temperature is varied from 120 K to 1200 K and the implanted flux of 100 eV He is varied from \$\$10{\textasciicircum}\{17\}{\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$to \$\$5 {\textbackslash}times 10{\textasciicircum}\{21\}{\textbackslash}, \{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$. Bubble mean size increases as a power law of time whereas the bubble density reaches a maximum. The maximum He content in bubbles was approximately \$\$4 {\textbackslash}times 10{\textasciicircum}\{8\}\$\$He at \$\$5 {\textbackslash}times 10{\textasciicircum}\{21\}{\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}{\textbackslash}, {\textbackslash}text\{s\}{\textasciicircum}\{-1\}\}\$\$. After 1 h of exposure, the helium inventory varies from \$\$5 {\textbackslash}times 10{\textasciicircum}\{16\} {\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}\}\$\$at low flux and high temperature to \$\$10{\textasciicircum}\{25\} {\textbackslash},\{{\textbackslash}text\{m\}{\textasciicircum}\{-2\}\}\$\$at high flux and low temperature. The bubbles inventory varies from \$\$5 {\textbackslash}times 10{\textasciicircum}\{12\}\$\$bubbles m\$\${\textasciicircum}\{-2\}\$\$to \$\$2 {\textbackslash}times 10{\textasciicircum}\{19\}\$\$bubbles m\$\${\textasciicircum}\{-2\}\$\$. Comparison with experimental measurements is performed. The bubble density simulated by the model is in quantitative agreement with experiments.}, - language = {en}, - number = {1}, - urldate = {2021-11-10}, - journal = {Scientific Reports}, - author = {Delaporte-Mathurin, Rémi and Ialovega, Mykola and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Bernard, Elodie and Martin, Céline and Grisolia, Christian}, - month = jul, - year = {2021}, - keywords = {Applied mathematics, Materials science, Mathematics and computing, Theory and computation}, - pages = {14681}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\C9JC5HZP\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BU5M53CW\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QGSKDP59\\s41598-021-93542-9.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2NCIHGZF\\Delaporte-Mathurin et al. - 2021 - Influence of exposure conditions on helium transpo.pdf:application/pdf}, +@article{taylor_investigating_2019, + title = {Investigating {Helium} {Bubble} {Nucleation} and {Growth} through {Simultaneous} {In}-{Situ} {Cryogenic}, {Ion} {Implantation}, and {Environmental} {Transmission} {Electron} {Microscopy}}, + volume = {12}, + issn = {1996-1944}, + url = {https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6719068/}, + doi = {10.3390/ma12162618}, + abstract = {Palladium can readily dissociate molecular hydrogen at its surface, and rapidly accept it onto the octahedral sites of its face-centered cubic crystal structure. This can include radioactive tritium. As tritium β-decays with a half-life of 12.3 years, He-3 is generated in the metal lattice, causing significant degradation of the material. Helium bubble evolution at high concentrations can result in blister formation or exfoliation and must therefore be well understood to predict the longevity of materials that absorb tritium. A hydrogen over-pressure must be applied to palladium hydride to prevent hydrogen from desorbing from the metal, making it difficult to study tritium in palladium by methods that involve vacuum, such as electron microscopy. Recent improvements in in-situ ion implantation Transmission Electron Microscopy (TEM) allow for the direct observation of He bubble nucleation and growth in materials. In this work, we present results from preliminary experiments using the new ion implantation Environmental TEM (ETEM) at the University of Huddersfield to observe He bubble nucleation and growth, in-situ, in palladium at cryogenic temperatures in a hydrogen environment. After the initial nucleation phase, bubble diameter remained constant throughout the implantation, but bubble density increased with implantation time. β-phase palladium hydride was not observed to form during the experiments, likely indicating that the cryogenic implantation temperature played a dominating role in the bubble nucleation and growth behavior.}, + number = {16}, + urldate = {2019-10-31}, + journal = {Materials}, + author = {Taylor, Caitlin A. and Briggs, Samuel and Greaves, Graeme and Monterrosa, Anthony and Aradi, Emily and Sugar, Joshua D. and Robinson, David B. and Hattar, Khalid and Hinks, Jonathan A.}, + month = aug, + year = {2019}, + pmid = {31426387}, + pmcid = {PMC6719068}, + keywords = {Experiment, Bubble}, + file = {Taylor et al. - 2019 - Investigating Helium Bubble Nucleation and Growth .pdf:D\:\\Logiciels\\data_zotero\\storage\\YM8TQXXI\\Taylor et al. - 2019 - Investigating Helium Bubble Nucleation and Growth .pdf:application/pdf}, } -@misc{noauthor_influence_nodate, - title = {Influence of exposure conditions on helium transport and bubble growth in tungsten {\textbar} {Scientific} {Reports}}, - url = {https://www.nature.com/articles/s41598-021-93542-9}, - urldate = {2021-11-10}, +@article{cui_thermal_2017, + title = {Thermal conductivity reduction of tungsten plasma facing material due to helium plasma irradiation in {PISCES} using the improved 3-omega method}, + volume = {486}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311516303488}, + doi = {10.1016/j.jnucmat.2017.01.023}, + abstract = {The near-surface region of plasma facing material (PFM) plays an important role in thermal management of fusion reactors. In this work, we measured thermal conductivity of tungsten (W) surface layers damaged by He plasma in PISCES at UCSD. We studied the damage effect on both bulk, and thin film, W. We observed that the surface morphology of both bulk and thin film was altered after exposure to He plasma with the fluence of 1 × 1026 m−2 (bulk) and 2 × 1024 m−2 (thin film). Transmission electron microscopy (TEM) analysis reveals that the depth of the irradiation damaged layer was approximately 20 nm on the bulk W exposed to He plasma at 773 K for 2000 s. In order to measure the thermal conductivity of this exceedingly thin damaged layer in the bulk W, we adopted the well-established ‘3-omega’ method and employed novel nanofabrication techniques to improve the measurement sensitivity. For the damaged W thin film sample, we measured the reduction in electrical conductivity and used the Wiedemann-Franz (W-F) law to extract the thermal conductivity. Results from both measurements show that thermal conductivity in the damaged layers was reduced by at least ∼80\% compared to that of undamaged W. This large reduction in thermal conductivity can be attributed to the scattering of electrons, the dominant heat carriers in W, caused by defects introduced by He plasma irradiation.}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Cui, Shuang and Simmonds, Michael and Qin, Wenjing and Ren, Feng and Tynan, George R. and Doerner, Russell P. and Chen, Renkun}, + month = apr, + year = {2017}, + keywords = {Experiment}, + pages = {267--273}, + file = {Cui et al. - 2017 - Thermal conductivity reduction of tungsten plasma .pdf:D\:\\Logiciels\\data_zotero\\storage\\JXBSAZE6\\Cui et al. - 2017 - Thermal conductivity reduction of tungsten plasma .pdf:application/pdf}, } -@article{arredondo_preliminary_2021, - title = {Preliminary estimates of tritium permeation and retention in the first wall of {DEMO} due to ion bombardment}, - volume = {28}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121001125}, - doi = {10.1016/j.nme.2021.101039}, - abstract = {Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling system, etc. Structural and plasma-facing components will act as a tritium sink, as tritium will be accumulated in the bulk of these components due to energetic particle bombardment and may permeate out of the vacuum system. The design of the plasma-facing components will consequently directly influence the plant lifetime, operational safety and cost of any future power plant. Therefore, modeling of tritium retention and permeation in these components is required for the engineering designs of the tritium breeding and safety systems. In this work, the diffusion-transport code TESSIM-X is benchmarked against the well-established TMAP7 code and a comparison with a simplified DEMO-relevant test case is performed. The use of either code for modeling of DEMO conditions is discussed. Following this, TESSIM-X is used to provide a preliminary assessment of tritium permeation and retention in the DEMO first wall, based on the current WCLL (Water Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed) breeding blanket designs.}, +@article{tokunaga_synergistic_2004, + series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)}, + title = {Synergistic effects of high heat loading and helium irradiation of tungsten}, + volume = {329-333}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311504003149}, + doi = {10.1016/j.jnucmat.2004.04.178}, + abstract = {High heat flux experiments using a helium beam have been carried out on powder metallurgy tungsten. The energy of He is 19 keV. He beam flux and heat flux at the beam center is 2.0×1021 He/m2s and 6.0 MW/m2, respectively. Beam duration is 3.0–3.9 s and interval of beam shot start is 30 s. The samples are irradiated up to a fluence of 1022–1024 He/m2 by the repeated irradiation pulses. In addition to the He beam irradiation, high heat flux experiments using hydrogen and electron beams have also been carried out on the samples. After the irradiation, surface modification by the irradiation has been investigated. Surface modification by helium and hydrogen beams is completely different from results of electron beam heating. In particular, helium beam heating causes remarkably surface modification such as a fine-scale rough surface at a peak temperature above 2400 °C.}, language = {en}, - urldate = {2021-11-10}, - journal = {Nuclear Materials and Energy}, - author = {Arredondo, R. and Schmid, K. and Subba, F. and Spagnuolo, G. A.}, - month = sep, - year = {2021}, - keywords = {DEMO, First wall, Permeation, Retention, TMAP, TESSIM}, - pages = {101039}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\65W4FVGT\\Arredondo et al. - 2021 - Preliminary estimates of tritium permeation and re.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\J7A87PRE\\S2352179121001125.html:text/html}, + urldate = {2019-11-04}, + journal = {Journal of Nuclear Materials}, + author = {Tokunaga, K and Tamura, S and Yoshida, N and Ezato, K and Taniguchi, M and Sato, K and Suzuki, S and Akiba, M}, + month = aug, + year = {2004}, + keywords = {Experiment, Blistering}, + pages = {757--760}, + file = {Tokunaga et al. - 2004 - Synergistic effects of high heat loading and heliu.pdf:D\:\\Logiciels\\data_zotero\\storage\\2GRVRL38\\Tokunaga et al. - 2004 - Synergistic effects of high heat loading and heliu.pdf:application/pdf}, } -@article{dhard_plasma-wall_2021, - title = {Plasma-wall interaction studies in {W7}-{X}: main results from the recent divertor operations}, - volume = {96}, - issn = {1402-4896}, - shorttitle = {Plasma-wall interaction studies in {W7}-{X}}, - url = {https://doi.org/10.1088/1402-4896/ac35c0}, - doi = {10.1088/1402-4896/ac35c0}, - abstract = {Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D geometry of W7-X were carried out by in situ spectroscopic observations, exhaust gas analysis and post-mortem measurements on a large number of plasma-facing components extracted after campaigns. The investigations showed that the divertor strike line areas on the divertor targets appeared to be the major source of carbon impurities. After multistep erosion and deposition events, carbon was found to be deposited largely at the first wall components, with thick deposits of {\textgreater}1 μm on some baffle tiles, moderate deposits on toroidal closure tiles and thin deposits at the heat shield tiles and the outer wall panels. Some amount of the eroded carbon was pumped out via the vacuum pumps as volatile hydrocarbons and carbon oxides (CO, CO2) formed due to the chemical processes. Boron was introduced by three boronizations and one boron powder injection experiment. Thin boron-dominated layers were found on the inner heat shield and the outer wall panels, some boron was also found at the test divertor unit and in redeposited layers together with carbon. Local erosion/deposition and global migration processes were studied using field-line transport simulations, analytical estimations, 3D-WallDYN and ERO2.0 modeling in standard magnetic field configuration.}, +@article{singh_nucleation_1984, + title = {Nucleation of helium bubbles on dislocations, dislocation networks and dislocations in grain boundaries during 600 {MeV} proton irradiation of aluminium}, + volume = {125}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/0022311584905567}, + doi = {10.1016/0022-3115(84)90556-7}, + abstract = {High-purity aluminium (99.9999\%) was irradiated with 600 MeV protons with a damage rate of 3.5 × 10−6dpa/s. Irradiation with 600 MeV protons produces helium and hydrogen at the rate of 140 and 615 appm per dpa, respectively. Specimens irradiated at temperatures in the range 116 to 318 °C to doses in the range 0.04 to 5 dpa were examined in a transmission electron microscope (TEM). The TEM investigation has shown that helium bubbles are formed on dislocations in the grains as well as dislocations in the grain boundaries. Dislocation nodal points whether present in dislocation walls or in grain boundaries are found to be the most favourable sites for bubble nucleation. The mean diameter of the bubbles on individual dislocation lines are found to be larger than those for the bubbles in the matrix. The bubble size and density on grain boundaries vary from boundary to boundary. The size of these bubbles on the boundaries is larger than or equal to the size of those in the matrix. It is suggested that helium atoms once arrived at a dislocation remain bound to the dislocation line but at the same time remain mobile within the dislocation core; the bubble nucleation behaviour in the core would thus be affected by the core structure of the different dislocations. An estimate of the effective helium diffusion in the dislocations relative to that in the lattice has been made on the basis of the measured bubble parameters and the width of the bubble-denuded zone along dislocation lines; the diffusion coefficient of helium in the dislocations is found to be about the same as that in the lattice.}, language = {en}, - number = {12}, - urldate = {2021-12-09}, - journal = {Physica Scripta}, - author = {Dhard, C. P. and Brezinsek, S. and Mayer, M. and Naujoks, D. and Masuzaki, S. and Zhao, D. and Yi, R. and Oelmann, J. and Schmid, K. and Romazanov, J. and Pardanaud, C. and Kandler, M. and Kharwandikar, A. K. and Schlisio, G. and Volzke, O. and Grote, H. and Gao, Y. and Rudischhauser, L. and Goriaev, A. and Wauters, T. and Kirschner, A. and Sereda, S. and Wang, E. and Rasinski, M. and Dittmar, T. and Motojima, G. and Hwangbo, D. and Kajita, S. and Balden, M. and Burwitz, V. V. and Neu, R. and Linsmeier, Ch and Team, the W7-X.}, - month = nov, - year = {2021}, - note = {Publisher: IOP Publishing}, - pages = {124059}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SM7M5FVJ\\Dhard et al. - 2021 - Plasma-wall interaction studies in W7-X main resu.pdf:application/pdf}, + number = {3}, + urldate = {2019-10-31}, + journal = {Journal of Nuclear Materials}, + author = {Singh, B. N. and Leffers, T. and Green, W. V. and Victoria, M.}, + month = aug, + year = {1984}, + keywords = {Experiment, Bubble}, + pages = {287--297}, + file = {Singh et al. - 1984 - Nucleation of helium bubbles on dislocations, disl.pdf:D\:\\Logiciels\\data_zotero\\storage\\NJWFEPJY\\Singh et al. - 1984 - Nucleation of helium bubbles on dislocations, disl.pdf:application/pdf}, } -@article{dark_influence_2021, - title = {Influence of hydrogen trapping on {WCLL} breeding blanket performances}, - volume = {61}, - copyright = {All rights reserved}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/ac28b0}, - doi = {10.1088/1741-4326/ac28b0}, - abstract = {Tritium transport simulations in water-cooled lithium lead (WCLL) breeding blankets have been performed with FESTIM. Fluid dynamics and heat transfer were coupled to evaluate how temperature and LiPb velocity fields affect tritium transport. The 2D WCLL model consisted of tungsten, EUROFER and liquid LiPb. Tritium inventories and permeation fluxes have been computed and the influence of trapping effects in solid domains was highlighted. It was evaluated that inclusion of trapping mechanisms increases inventory values by 15\% and delays permeation to the cooling channels. A parametric study was conducted to investigate the impact of the uncertainty in the literature (2 orders of magnitude) regarding hydrogen solubility in LiPb on these quantities. Varying the lithium lead solubility over the range found in the literature was found to vary the EUROFER inventory by a factor of 25. Permeation fluxes to the coolant channels was found to vary over a factor of 3.}, - language = {en}, - number = {11}, - urldate = {2021-12-08}, - journal = {Nuclear Fusion}, - author = {Dark, James and Delaporte-Mathurin, Remi and Charles, Yann and Hodille, Etienne A. and Grisolia, Christian and Mougenot, Jonathan}, - month = oct, - year = {2021}, - note = {Publisher: IOP Publishing}, - pages = {116076}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ICCH6ZVV\\Dark et al. - 2021 - Influence of hydrogen trapping on WCLL breeding bl.pdf:application/pdf}, +@article{kornelsen_interaction_1972, + title = {The interaction of injected helium with lattice defects in a tungsten crystal}, + volume = {13}, + issn = {0033-7579}, + url = {https://doi.org/10.1080/00337577208231184}, + doi = {10.1080/00337577208231184}, + abstract = {Helium injected into tungsten has been found to undergo rapid interstitial diffusion at room temperature unless it encounters lattice defects. This effect has been used in a study of the lattice damage produced near a (100) tungsten surface by the impact of small numbers of 5 keV heavy ions. The helium, injected as 250eV ions, does not itself produce any observable damage, but is trapped in that created by the prior heavy ion bombardment. Thermal desorption spectra obtained by raising the crystal temperature at 40°K/sec show that the helium is bound with several discrete energies. Attempts to correlate the binding states with particular lattice defects have been made by varying the damage anneal temperature, the helium dose, the helium injection temperature and the mass of the damaging ion. The results suggest that all of the entrapment occurs at defects of the vacancy type, and that the binding energy is modified by parameters that change the available vacancy volume. In particular there is evidence that at least two and possibly three helium atoms can be trapped in a single vacancy, that two types of divacancies exist, and that vacancies become trapped in the strain field of large impurity atoms. It also appears that at sufficiently high helium doses ({\textgreater} 1014 ions/ cm2), any of the trapping sites can act as nuclei for the formation of helium bubbles.}, + number = {3-4}, + urldate = {2019-10-25}, + journal = {Radiation Effects}, + author = {Kornelsen, E. V.}, + month = apr, + year = {1972}, + keywords = {Experiment, Bubble}, + pages = {227--236}, + file = {Kornelsen - 1972 - The interaction of injected helium with lattice de.pdf:D\:\\Logiciels\\data_zotero\\storage\\ZKHTEVL3\\Kornelsen - 1972 - The interaction of injected helium with lattice de.pdf:application/pdf}, } -@article{delaporte-mathurin_fuel_2021, - title = {Fuel retention in {WEST} and {ITER} divertors based on {FESTIM} monoblock simulations}, - volume = {61}, - copyright = {All rights reserved}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/ac2bbd}, - doi = {10.1088/1741-4326/ac2bbd}, - abstract = {The influence of the input power (IP), puffing rate and neutral pressure on the fuel (hydrogen isotopes) inventory of the WEST and ITER divertors is investigated. For the chosen range of parameters (relatively low temperature at the strike points), the inventory of the WEST divertor evolves as the power 0.2 of the puffing rate and as the power 0.3 of the IP. The inventory at the strike points is highly dominated by ions whereas it is dominated by neutrals in the private zone. Increasing the fuelling rate increases the retention in the private zone and decreases slightly the retention at the strike points. Increasing the IP increases the inventory at the strike points and does not affect much the inventory at the private flux region. The inventory of the ITER divertor is not strongly dependent on the divertor neutral pressure. The inventory increases from 0 Pa to 7 Pa and then decreases slightly from 7 Pa to 10 Pa. After 107 s of continuous exposure, the maximum inventory in the ITER divertor was found to be 14 g. The inventory is not maximum at the strike points due to the high surface temperature of the monoblocks in this region. The maximum accumulation of H in the ITER divertor is below 5 mg per 400 s discharge and below 2 mg per 400 s discharge after 200 discharges.}, - language = {en}, - number = {12}, - urldate = {2022-02-24}, - journal = {Nuclear Fusion}, - author = {Delaporte-Mathurin, Rémi and Yang, Hao and Denis, Julien and Dark, James and Hodille, Etienne A. and Temmerman, Gregory De and Bonnin, Xavier and Mougenot, Jonathan and Charles, Yann and Bufferand, Hugo and Ciraolo, Guido and Grisolia, Christian}, - month = oct, - year = {2021}, - note = {Publisher: IOP Publishing}, - pages = {126001}, - file = {Delaporte-Mathurin_2021_Nucl._Fusion_61_126001.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\479BUFYN\\Delaporte-Mathurin_2021_Nucl._Fusion_61_126001.pdf:application/pdf}, +@article{qu_degradation_2018, + title = {Degradation of thermal conductivity of the damaged layer of tungsten irradiated by helium-plasma}, + volume = {137}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618306045}, + doi = {10.1016/j.fusengdes.2018.08.014}, + abstract = {Pure tungsten samples were irradiated by helium plasma in the linear plasma device PSI-2 with an ion energy of 40 eV and a flux of 1.1 × 1022 m−2s−1. The irradiation temperature was from 523 K to 773 K and the fluence was from 1.0 × 1025 to 1.0 × 1026 m−2. A damaged layer of 10 nm thickness was formed on the sample surface with a destroyed crystalline structure. Helium-bubbles and surface modification in nanoscale were observed. Thermal conductivities of the ultra-thin damaged layers were measured by the transient thermoreflectance technique. Result shows that the thermal conductivity reduced two orders of magnitude compared to the bulk value and decreased with increasing irradiation temperature and fluence. Moreover, the helium-irradiated samples were exposed to ELM-like heat load produced by electron beam on EMS-60. The pulse length was 1 ms and each sample was exposed to 5 pulses. Melting occurred under power density of 1.7 GW m−2. As the thermal conductivity of the damaged layer decreased, the molten bath of the irradiated sample deepened. The degraded thermal conductivity led to a lower melting threshold. The characterization of the thermal conductivity of the damaged layer induced by the plasma irradiation is a promising way to estimate the damage level, as well as the failure threshold, of the plasma facing components.}, + urldate = {2019-10-07}, + journal = {Fusion Engineering and Design}, + author = {Qu, Shilian and Sun, Hao and Kreter, Arkadi and Yuan, Yue and Cheng, Long and Huang, Zhengxing and Xu, Ben and Chen, Wanqi and Cui, Wei and Tang, Zhenan and Jia, Yuzhen and Lian, YouYun and Liu, Xiang and Liu, Wei}, + month = dec, + year = {2018}, + keywords = {Experiment}, + pages = {97--103}, + annote = { +In this paper the influence of He plasma exposure on thermal conductivity of tungsten is investigated. +Helium bubbles and surface modification is observed. +Samples have been exposed to ELM-like heat loads produced by electron beam. +Melting is observed as the thermal conductivity decreases. +Measuring the thermal conductivity seems to be a good way to estimate the damage level induced by He exposure. +Thermal conductivity is reduced by 2 orders of magnitude compared to the one in the bulk. +Thermal conductivity decreases with the increasing implantation temperature. +TDS spectrum are shown and were performed from room temperature up to 1423 K at different implantation temperatures. +He bubbles' sizes and volume fraction (as well as other defects) increase with increasing irradiation temperature and fluence. +}, + file = {Qu et al. - 2018 - Degradation of thermal conductivity of the damaged.pdf:D\:\\Logiciels\\data_zotero\\storage\\NSNCFPG4\\Qu et al. - 2018 - Degradation of thermal conductivity of the damaged.pdf:application/pdf}, } -@article{kremer_influence_2022, - title = {Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179122000242}, - doi = {10.1016/j.nme.2022.101137}, - abstract = {We studied the influence of thin, electro-chemically grown tungsten (W) surface oxide films on hydrogen isotope release from W. As deuterium (D) reservoir underneath the oxide, we used a defect-rich, ion-irradiated W layer that was filled with D prior to oxidation. Several oxide films with thicknesses between 5 and 100nm were studied and compared with tungsten with a natural oxide film. The release of D through the oxide film was analyzed with thermal desorption spectroscopy (TDS). The depth-resolved concentration profiles of D in the sample were measured with nuclear reaction analysis at all experimental steps. Changes of the morphology of the oxide film due to the release of D were investigated with scanning electron microscopy (SEM). In TDS studies, we found that the thin oxide films significantly influence the release behavior of D from W. The first D release peak (at 560K) is shifted towards higher temperature (or later times) with increasing oxide thickness. This indicates that the oxide film acts as both a D reservoir and a transport barrier that delays D release at temperatures above 475K. At this temperature, D also starts to interact chemically with the oxide film and is released not only as HD or D2 but also in the form of heavy water (HDO and D2O). Above 700K, D is released only in form of heavy water as long as enough oxide is available. Accordingly, SEM images after TDS show a strong modification of the oxide film. For film thicknesses of 5-10nm, all oxide is removed from the surface and smooth metallic W remains. For 15nm, the surface is still partially covered by oxide islands with several micrometer of metallic W between them. From the fact that D is still only released as heavy water at high temperatures, we conclude that the mobility of D atoms at the surface is very high. Even D atoms that surface far from an oxide island apparently travel along the surface to form an O-D group at the W oxide before they recombine with another D atom to form water. Our results indicate that the oxide film becomes relevant for the D release during TDS if the ratio of O atoms on the surface to D atoms in the sample is larger than 5-10 \%. Consequently, even the natural oxide film (1-2nm) that forms on W upon contact with air may significantly influence the D release spectra from TDS for experiments with low D retention.}, +@phdthesis{sefta_surface_2013, + title = {Surface {Response} of {Tungsten} to {Helium} and {Hydrogen} {Plasma} {Flux} as a {Function} of {Temperature} and {Incident} {Kinetic} {Energy}}, + url = {https://escholarship.org/uc/item/0kw3r768}, + abstract = {Tungsten is a leading candidate material for the diverter in future nuclear fusion reactors. Previous experiments have demonstrated that surface defects and bubbles form in tungsten when ex- posed to helium and hydrogen plasmas, even at modest ion energies. In some regimes, between 1000K and 2000K, and for He energies below 100eV, "fuzz" like features form. The mechanisms leading to these surfaces comprised of nanometer sized tungsten tendrils which include visible helium bubbles are not currently known. The role of helium bubble formation in tendril morphology could very likely be the starting point of these mechanisms. Using Molecular dynamics (MD) simulations, the role of helium and hydrogen exposure in the initial formation mechanisms of tungsten "fuzz" are investigated. Molecular dynamics simulations are well suited to describe the time and length scales associated with initial formation of helium clusters that eventually grow to nano-meter sized helium bubbles. MD simulations also easily enable the modeling of a variety of surfaces such as single crystals, grain boundaries or "tendrils".While the sputtering yield of tungsten is generally low, previous observations of surface modification due to plasma exposure raise questions about the effects of surface morphology and sub-surface helium bubble populations on the sputtering behavior. Results of computational molecular dynamics are reported that investigate the influence of sub-surface helium bubble distributions on the sputtering yield of tungsten (100) and (110) surfaces induced by helium ion exposure in the range of 300 eV to 1 keV. The calculated sputtering yields are in reasonable agreement with a wide range of experimental data; but do not show any significant variation as a result of the pre-existing helium bubbles.Molecular dynamics simulations reveal a number of sub-surface mechanisms leading to nanometer- sized "fuzz" in tungsten exposed to low-energy helium plasmas. We find that during the bubble formation process, helium clusters create self-interstitial defect clusters in tungsten by a trap mutation process, followed by the migration of these defects to the surface that leads to the formation of layers of adatom islands on the tungsten surface. As the helium clusters grow into nanometer sized bubbles, their proximity to the surface and extremely high gas pressures can cause them to rupture the surface thus enabling helium release. Helium bubble bursting induces additional surface damage and tungsten mass loss which varies depending on the nature of the surface. We then show tendril-like geometries have surfaces that are more resilient to helium clustering and bubble formation and rupture. Finally, the study includes hydrogen to reveal the effect of a mixed 90\%H-10\%He plasma mix on the tungsten surface. We find that hydrogen greatly affects the tungsten surface, with a near surface hydrogen saturation layer, and that helium clusters still form and are attractive trapping sites for hydrogen.Molecular dynamics simulations have also investigated the effect of sub-surface helium bubble evolution on tungsten surface morphology. The helium bubble/tungsten surface interaction has been systematically studied to determine how parameters such as bubble shape and size, temperature, tungsten surface orientation and ligament thickness above the bubble impact bubble stability and surface evolution. The tungsten surface is roughened by a combination of adatom islands, craters and pinholes. The study provides insight into the mechanisms and conditions leading to various tungsten topology changes, most notably the formation of nanoscale fuzz.An atomistic study of the mechanisms behind initial phases of tungsten nano-fuzz growth has determined that tungsten surfaces are affected by sub-displacement energy helium and hydrogen fluxes through a series of mechanisms. Sub-surface helium atom clustering, bubble nucleation, growth and rupture lead to tungsten surface deformation. Helium clustering processes vary near grain boundaries or in tendril-like surface geometries. In the presence of hydrogen, these mechanisms are coupled with hydrogen surface saturation. Finally, further investigation to connect these atomistic mechanisms to nano-size tungsten fuzz growth is needed to get a comprehensive under- standing of the effects of low energy helium and hydrogen on tungsten.}, language = {en}, - urldate = {2022-02-21}, - journal = {Nuclear Materials and Energy}, - author = {Kremer, K. and Brucker, M. and Jacob, W. and Schwarz-Selinger, T.}, - month = feb, - year = {2022}, - keywords = {NRA, TDS, D release from tungsten, deuterium release, hydrogen isotope release, Hydrogen Isotope retention, thin films, tungsten oxide, water formation}, - pages = {101137}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\78CIJ98Z\\S2352179122000242.html:text/html}, + urldate = {2019-10-28}, + school = {UC Berkeley}, + author = {Sefta, Faiza}, + year = {2013}, + keywords = {Molecular Dynamics, Bursting, Blistering, Bubble}, + file = {Sefta - 2013 - Surface Response of Tungsten to Helium and Hydroge.pdf:D\:\\Logiciels\\data_zotero\\storage\\DWFJ9TGD\\Sefta - 2013 - Surface Response of Tungsten to Helium and Hydroge.pdf:application/pdf}, } -@article{utili_design_2022, - title = {Design of the {Test} {Section} for the {Experimental} {Validation} of {Antipermeation} and {Corrosion} {Barriers} for {WCLL} {BB}}, - volume = {12}, - copyright = {http://creativecommons.org/licenses/by/3.0/}, - issn = {2076-3417}, - url = {https://www.mdpi.com/2076-3417/12/3/1624}, - doi = {10.3390/app12031624}, - abstract = {Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction. Several technologies were investigated as antipermeation and corrosion barriers to reduce the tritium permeation flux from the breeder into the PHTS. Within this frame, alumina coating manufactured by Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) are two of the main candidates for the Water Cooled Lithium Lead (WCLL) Breeder Blanket (BB). In order to validate the performance of the coatings on relevant WCLL BB geometries, a mock-up was designed and will be characterized in an experimental facility operating with flowing lithium-lead, called TRIEX-II. The present work aims to illustrate the preliminary engineering design of a WCLL BB mock-up in order to deeply investigate permeation of hydrogen isotopes through PHTS water pipes. The permeation tests are planned in the temperature range between 330 and 500 °C, with hydrogen and deuterium partial pressure in the range of 1–1000 Pa. The hydrogen isotopes transport analysis carried out for the design and integration of the mock-up in TRIEX-II facility is also shown.}, +@article{hu_dynamics_2014, + title = {Dynamics of small mobile helium clusters near tungsten surfaces}, + volume = {626}, + issn = {0039-6028}, + url = {http://www.sciencedirect.com/science/article/pii/S0039602814000867}, + doi = {10.1016/j.susc.2014.03.020}, + abstract = {We report the results of a systematic atomic-scale analysis of the dynamics of small mobile helium clusters in tungsten, near tungsten surfaces. These helium clusters are attracted to tungsten surfaces due to an elastic interaction force that drives surface segregation. As the clusters migrate toward the surface, trap mutation and cluster dissociation are activated at rates higher than in the bulk. These kinetic processes are responsible for important structural, morphological, and compositional features in plasma-exposed tungsten, including surface adatoms, near-surface immobile helium–vacancy complexes, and retained helium content. Detailed results are presented for di-helium and tri-helium clusters near low-Miller-index tungsten surfaces.}, language = {en}, - number = {3}, - urldate = {2022-02-15}, - journal = {Applied Sciences}, - author = {Utili, Marco and Alberghi, Ciro and Candido, Luigi and Di Fonzo, Fabio and Papa, Francesca and Venturini, Alessandro}, - month = jan, - year = {2022}, - note = {Number: 3 -Publisher: Multidisciplinary Digital Publishing Institute}, - keywords = {DEMO, ITER, WCLL, antipermeation barrier, corrosion barrier, lithium-lead}, - pages = {1624}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EW8UW2HZ\\1624.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2FD3KPJT\\Utili et al. - 2022 - Design of the Test Section for the Experimental Va.pdf:application/pdf}, + urldate = {2019-10-28}, + journal = {Surface Science}, + author = {Hu, Lin and Hammond, Karl D. and Wirth, Brian D. and Maroudas, Dimitrios}, + month = aug, + year = {2014}, + keywords = {Molecular Dynamics}, + pages = {L21--L25}, + annote = { +This paper is a modelling work at atomistic scale (MD). +In this work di-helium and tri-helium clusters are studied near tungsten surfaces. +Several mechanisms are highlighted. +Several activation energies are given. +}, + file = {Hu et al. - 2014 - Dynamics of small mobile helium clusters near tung.pdf:D\:\\Logiciels\\data_zotero\\storage\\UXJARE84\\Hu et al. - 2014 - Dynamics of small mobile helium clusters near tung.pdf:application/pdf}, } -@article{bae_arc_2022, - title = {{ARC} reactor neutronics multi-code validation}, +@article{krasheninnikov_helium_2014, + title = {On helium cluster dynamics in tungsten plasma facing components of fusion devices}, + volume = {54}, issn = {0029-5515}, - url = {http://iopscience.iop.org/article/10.1088/1741-4326/ac536a}, - doi = {10.1088/1741-4326/ac536a}, - abstract = {The affordable, robust, compact (ARC) reactor is a tokamak fusion reactor concept currently under development by Commonwealth Fusion Systems (CFS)and Massachusetts Institute of Technology. There are three important neutronics considerations for the operation of the ARC reactor: (1) breeding of enough tritium in the blanket to sustain the D-T reaction in the plasma; (2) ensuring low fluence on the superconducting toroidal field coils; and (3) assessing neutron volumetric heating in structural components. This work aims to perform a validation of the neutronics analysis approach by code-to-code comparison. State-of-the-art software stacks are employed for the neutronics analysis of the ARC reactor, and a computer-aided design (CAD) model is used directly for Monte Carlo (MC) neutron transport calculations. Three software stacks, Attila-MCNP, OpenMC-DAGMC, and Shift-DAGMC, are used to perform neutronic analysesof a 90°sector CAD model of the ARC reactor. Results show that the flux tallies calculated by the three software stacks are very close. Also, the volumetric heatingand tritium breeding values have less than 0.6\% relative difference between codes.}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/54/7/073019}, + doi = {10.1088/0029-5515/54/7/073019}, + abstract = {This paper describes the dynamics of helium clustering behaviour within either a nanometer-sized tendril of fuzz, or a half-space domain, as predicted by a reaction–diffusion model. This analysis has identified a dimensionless parameter, PΔ, which is a balance of the reaction and diffusion actions of insoluble He in a metal matrix and which governs the self-trapping effects of He into growing bubbles within a tendril. The impact of He self-trapping, as well as trapping caused by pre-existing traps in the form of lattice defects or clusters of impurities, within a half-space domain results in the formation of a densely packed layer of nanometer-sized bubbles with high number density. This prediction is consistent with available experimental observations in which a dense zone of helium bubbles is observed in tungsten, which are compared to estimates of the layer characteristics. Direct numerical simulation of the reaction–diffusion cluster dynamics supports the analysis presented here.}, language = {en}, - urldate = {2022-02-10}, + number = {7}, + urldate = {2019-10-28}, journal = {Nuclear Fusion}, - author = {Bae, Jin Whan and Peterson, Ethan and Shimwell, Jonathan}, - year = {2022}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2AGWQXW7\\Bae et al. - 2022 - ARC reactor neutronics multi-code validation.pdf:application/pdf}, -} - -@article{yamanishi_hydrogen_1983, - title = {Hydrogen {Permeation} and {Diffusion} through {Pure} {Fe}, {Pure} {Ni} and {Fe}\–{Ni} {Alloys}}, - volume = {24}, - issn = {0021-4434, 2432-4701}, - url = {https://www.jstage.jst.go.jp/article/matertrans1960/24/1/24_1_49/_article}, - doi = {10.2320/matertrans1960.24.49}, - language = {en}, - number = {1}, - urldate = {2022-02-05}, - journal = {Transactions of the Japan Institute of Metals}, - author = {Yamanishi, Y. and Tanabe, T. and Imoto, S.}, - year = {1983}, - pages = {49--58}, - file = {Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NPA6U8EC\\Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:application/pdf;Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\32XPKFQ9\\Yamanishi et al. - 1983 - Hydrogen Permeation and Diffusion through Pure Fe,.pdf:application/pdf}, + author = {Krasheninnikov, S. I. and Faney, T. and Wirth, B. D.}, + month = may, + year = {2014}, + keywords = {Cluster dynamics}, + pages = {073019}, + annote = { +This paper is really similar to the work of Faney et al as it shows very similar results but describes the involved equations very thoroughly. +Cluster dynamics with large number of clustesr. +In this work, clusters with more than 6 atoms in it are considered immobile. +}, + file = {Krasheninnikov et al. - 2014 - On helium cluster dynamics in tungsten plasma faci.pdf:D\:\\Logiciels\\data_zotero\\storage\\L9Y8JQR5\\Krasheninnikov et al. - 2014 - On helium cluster dynamics in tungsten plasma faci.pdf:application/pdf}, } -@techreport{san_marchi_technical_2012, - title = {Technical reference for hydrogen compatibility of materials.}, - url = {https://www.osti.gov/servlets/purl/1055634/}, - abstract = {The Technical Reference for Hydrogen Compatibility of Materials summarizes materials data related to hydrogen-assisted fracture (also called hydrogen embrittlement) in gaseous hydrogen environments, with emphasis on hydrogen permeation and structural properties. The Technical Reference generally does not provide specific recommendations for materials selection as the suitability of a given material depends on service conditions, in particular the mechanical and environmental conditions associated with a particular component, as well as the details of the materials microstructure. In substance, the Technical Reference is a collection of stand-alone documents organized by materials class, which have been compiled into this composite report. The individual sections are occasionally updated and new sections are added; the most recent versions are available from our website at http://www.ca.sandia.gov/matlsTechRef/. This compilation updates the previous composite release: SAND2008-1163.}, +@article{de_backer_modeling_2015, + series = {Proceedings of the 12th {International} {Conference} on {Computer} {Simulation} of {Radiation} {Effects} in {Solids}, {Alacant}, {Spain}, 8-13 {June}, 2014}, + title = {Modeling of helium bubble nucleation and growth in austenitic stainless steels using an {Object} {Kinetic} {Monte} {Carlo} method}, + volume = {352}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X14010118}, + doi = {10.1016/j.nimb.2014.11.110}, + abstract = {Implantation of 10keV helium in 316L steel thin foils was performed in JANNuS-Orsay facility and modeled using a multiscale approach. Density Functional Theory (DFT) atomistic calculations [1] were used to obtain the properties of He and He-vacancy clusters, and the Binary Collision Approximation based code MARLOWE was applied to determine the damage and He-ion depth profiles as in [2], [3]. The processes involved in the homogeneous He bubble nucleation and growth were defined and implemented in the Object Kinetic Monte Carlo code LAKIMOCA [4]. In particular as the He to dpa ratio was high, self-trapping of He clusters and the trap mutation of He-vacancy clusters had to be taken into account. With this multiscale approach, the formation of bubbles was modeled up to nanometer-scale size, where bubbles can be observed by Transmission Electron Microscopy. Their densities and sizes were studied as functions of fluence (up to 5×1019He/m2) at two temperatures (473 and 723K) and for different sample thicknesses (25–250nm). It appears that the damage is not only due to the collision cascades but is also strongly controlled by the He accumulation in pressurized bubbles. Comparison with experimental data is discussed and sensible agreement is achieved.}, language = {en}, - number = {SAND2012-7321, 1055634}, - urldate = {2022-02-04}, - author = {San Marchi, Christopher and Somerday, Brian}, - month = sep, - year = {2012}, - doi = {10.2172/1055634}, - pages = {SAND2012--7321, 1055634}, - file = {San Marchi et Somerday - 2012 - Technical reference for hydrogen compatibility of .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3KBKK3JA\\San Marchi et Somerday - 2012 - Technical reference for hydrogen compatibility of .pdf:application/pdf}, + urldate = {2019-10-28}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {De Backer, A. and Adjanor, G. and Domain, C. and Lescoat, M. L. and Jublot-Leclerc, S. and Fortuna, F. and Gentils, A. and Ortiz, C. J. and Souidi, A. and Becquart, C. S.}, + month = jun, + year = {2015}, + keywords = {Bubble, Monte Carlo}, + pages = {107--114}, + file = {De Backer et al. - 2015 - Modeling of helium bubble nucleation and growth in.pdf:D\:\\Logiciels\\data_zotero\\storage\\JKKUQFGT\\De Backer et al. - 2015 - Modeling of helium bubble nucleation and growth in.pdf:application/pdf}, } -@techreport{pattrick_calderoni_hydrogen_2010, - title = {Hydrogen {Permeability} of {Incoloy} {800H}, {Inconel} 617, and {Haynes} 230 {Alloys}}, - url = {http://www.osti.gov/servlets/purl/989876-0Fo4wi/}, +@article{kohnert_grouping_2016, + title = {Grouping techniques for large-scale cluster dynamics simulations of reaction diffusion processes}, + volume = {25}, + issn = {0965-0393}, + url = {https://iopscience.iop.org/article/10.1088/1361-651X/25/1/015008}, + doi = {10.1088/1361-651X/25/1/015008}, + abstract = {Cluster dynamics is a powerful, high fidelity, mesoscale method for modeling the kinetic evolution of point defects, impurities, and their clusters in materials and is commonly used in studying radiation damage. These methods excel at modeling nucleation, but often require too many equations to successfully model the long term growth and coarsening that govern microstructural evolution. One solution to this problem is to group equations into a coarser approximation of the cluster size distribution function which can reduce the cost of solution by many orders of magnitude. While such grouping methods have been advanced for a limited class of problems, no reliable method currently exists for the general case. This paper advances a framework for grouping arbitrary cluster dynamics problems, and develops several competing schemes based on that framework. These schemes are each evaluated against a variety of test problems designed to assess their accuracy, robustness, and efficiency.}, language = {en}, - number = {INL/EXT-10-19387, 989876}, - urldate = {2022-02-04}, - author = {{Pattrick Calderoni}}, - month = jul, - year = {2010}, - doi = {10.2172/989876}, - pages = {INL/EXT--10--19387, 989876}, - file = {Pattrick Calderoni - 2010 - Hydrogen Permeability of Incoloy 800H, Inconel 617.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VL32ZYBF\\Pattrick Calderoni - 2010 - Hydrogen Permeability of Incoloy 800H, Inconel 617.pdf:application/pdf}, + number = {1}, + urldate = {2019-10-25}, + journal = {Modelling and Simulation in Materials Science and Engineering}, + author = {Kohnert, Aaron A. and Wirth, Brian D.}, + month = dec, + year = {2016}, + keywords = {Cluster dynamics}, + pages = {015008}, + annote = { +This work is an attempt to reduce the computational cost of large cluster dynamics simulation. +One of the conclusions though is that the general scheme of cluster dynamics simulation is more robust and should be privileged. +}, + file = {Kohnert et Wirth - 2016 - Grouping techniques for large-scale cluster dynami.pdf:D\:\\Logiciels\\data_zotero\\storage\\QE6P64RJ\\Kohnert et Wirth - 2016 - Grouping techniques for large-scale cluster dynami.pdf:application/pdf}, } -@article{chen_diffusion_2017, - title = {Diffusion {Behaviors} of {Hydrogen} {Isotopes} in {Incoloy} {800H}: {A} {First}-{Principles} {Study}}, - volume = {2017}, - issn = {1687-6075, 1687-6083}, - shorttitle = {Diffusion {Behaviors} of {Hydrogen} {Isotopes} in {Incoloy} {800H}}, - url = {https://www.hindawi.com/journals/stni/2017/4038021/}, - doi = {10.1155/2017/4038021}, - abstract = {Incoloy 800H is one of the main stainless steel materials used in steam generators with High Temperature Reactor Pebble-bed Modules (HTR-PM). In this study, the diffusion behaviors of hydrogen isotopes in Incoloy 800H were investigated with first-principle calculations. Numerical results reveal that the starting and ending positions of the diffusion process are the two adjacent and most stable octahedral sites surrounded by Fe atoms and Ni atoms, and the diffusion follows an indirect path via the metastable tetrahedral sites and octahedral sites surrounded by Fe atoms and Cr atoms. The diffusion activation energies of hydrogen (H), deuterium (D), and tritium (T) in Incoloy 800H are investigated by first-principles calculations with the same approximate value of - - Q - = - 0.757 - -  eV; the diffusion coefficient frequency factors are also obtained with values of - - - - D - - - 0 - - - = - 1.56 - × - - - 10 - - - - - 6 - - - - , - - 1.10 - × - - - 10 - - - - - 6 - - - - , and - - 8.99 - × - - - 10 - - - - - 7 - - - -  (m - 2 - /s) for H, D, and T, respectively. Furthermore, the theoretical results are compared with the experimental data, and it is found that both are in agreement with each other. These results are very helpful for understanding the diffusion behaviors of hydrogen isotopes in Incoloy 800H and can be used to guide the tritium source term analysis of secondary circuits in HTR-PM, which are first studied from a microperspective.}, - language = {en}, - urldate = {2022-02-04}, - journal = {Science and Technology of Nuclear Installations}, - author = {Chen, Hongyu and Li, Hong and Li, Chuan and Cao, Jianzhu and Fang, Chao}, +@article{perez_mobility_2017, + title = {The mobility of small vacancy/helium complexes in tungsten and its impact on retention in fusion-relevant conditions}, + volume = {7}, + issn = {2045-2322}, + doi = {10.1038/s41598-017-02428-2}, + abstract = {Tungsten is a promising plasma facing material for fusion reactors. Despite many favorable properties, helium ions incoming from the plasma are known to dramatically affect the microstructure of tungsten, leading to bubble growth, blistering, and/or to the formation of fuzz. In order to develop mitigation strategies, it is essential to understand the atomistic processes that lead to bubble formation and subsequent microstructural changes. In this work, we use large-scale Accelerated Molecular Dynamics simulations to investigate small (N = 1,2) V N He M vacancy/helium complexes, which serve as the nuclei for larger helium bubble growth, over timescales reaching into the milliseconds under conditions typical of the operation of fusion reactors. These complexes can interconvert between different I L V N+L He M variants via Frenkel pair nucleation (leading to the creation of a additional vacancy/interstitial pair) and annihilation events; sequences of these events can lead to net migration of these embryonic bubbles. The competition between nucleation and annihilation produces a very complex dependence of the diffusivity on the number of heliums. Finally, through cluster dynamics simulations, we show that diffusion of these complexes provides an efficient pathway for helium release at fluxes expected in fusion reactors, and hence that accounting for the mobility of these complexes is crucial.}, + language = {eng}, + number = {1}, + journal = {Scientific Reports}, + author = {Perez, Danny and Sandoval, Luis and Blondel, Sophie and Wirth, Brian D. and Uberuaga, Blas P. and Voter, Arthur F.}, year = {2017}, - pages = {1--6}, - file = {Chen et al. - 2017 - Diffusion Behaviors of Hydrogen Isotopes in Incolo.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XJEXIDKM\\Chen et al. - 2017 - Diffusion Behaviors of Hydrogen Isotopes in Incolo.pdf:application/pdf}, + pmid = {28559588}, + pmcid = {PMC5449393}, + keywords = {Molecular Dynamics}, + pages = {2522}, + annote = { +This paper uses large molecular dynamic in order to investigate migration of small He clusters and their influence on He bubbles nucleation and moreover the He retention in tungsten. +Mobility of He clusters are calculated for different amount of He atoms in it. +For clusters of 8 up to 18 He atoms, the maximum diffusivity is approximately 10{\textasciicircum}-12, which is very low considering the order of magnitude of seconds. +There is though a complex dependency on number of vacancies in the cluster and number of atoms. +The study was limited to small complexes only. +In the Discussion part, it describes how to feed MD results in Xolotl. +Depth profiles of mobile and immobile He are shown. +One of the conclusions is that is it crucial to consider the mobility of larger clusters ({\textgreater}3 vacancies) in order to adequately predict evolution of He in tungsten. +If large clusters are considered immobile, the helium retention is overestimated and error increases with time (fluence). Concerning the shape of the profile there is smoother if the large clusters are considered mobile whereas it shows a strong peak at 1nm if not. +Effect of mobile vs immobile clusters is even greater at lower fluxes given that the clusters have more time to diffuse before encountering another one and nucleate. +}, + file = {Perez et al. - 2017 - The mobility of small vacancyhelium complexes in .pdf:D\:\\Logiciels\\data_zotero\\storage\\2TPUXBS5\\Perez et al. - 2017 - The mobility of small vacancyhelium complexes in .pdf:application/pdf}, } -@incollection{causey_416_2012, - address = {Oxford}, - title = {4.16 - {Tritium} {Barriers} and {Tritium} {Diffusion} in {Fusion} {Reactors}}, - isbn = {978-0-08-056033-5}, - url = {https://www.sciencedirect.com/science/article/pii/B9780080560335001166}, - abstract = {Tritium is a radioactive form of hydrogen. Because it is radioactive, its release to the environment must be minimized. Most of the materials used in fusion reactors are metals that have a relatively high permeability for tritium. The fusion community has been working on barrier materials to minimize tritium release by permeation through structural materials. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments. This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The parameters necessary for tritium release calculations for various regions of a fusion reactor are given.}, - language = {en}, - urldate = {2022-02-04}, - booktitle = {Comprehensive {Nuclear} {Materials}}, - publisher = {Elsevier}, - author = {Causey, R. A. and Karnesky, R. A. and San Marchi, C.}, - editor = {Konings, Rudy J. M.}, +@article{yang_kinetic_2017, + title = {Kinetic {Monte} {Carlo} {Simulations} of {Helium} {Cluster} {Nucleation} in {Tungsten} with {Preexisting} {Vacancies}}, + volume = {71}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST16-111}, + doi = {10.13182/FST16-111}, + abstract = {The object kinetic Monte Carlo code Kinetic Simulations Of Microstructure Evolution (KSOME) was used to study the subsurface helium clustering behavior in tungsten as a function of temperature, helium implantation rate, and vacancy concentration. The simulations evaluated helium implantation fluxes from 1022 to 1026 m−2 · s−1 at temperatures from 473 to 1473 K for 100-eV helium ions implanted below tungsten surfaces and for vacancy concentrations between 1 and 50 parts per million. Such vacancy concentrations far exceed thermodynamic equilibrium values but are consistent with supersaturated concentrations expected during concurrent, or preexisting, neutron irradiation. The thermodynamics and kinetic parameters to describe helium diffusion and clustering are input to KSOME based on values obtained from atomistic simulation results. These kinetic Monte Carlo results clearly delineate two different regimes of helium cluster nucleation, one dominated by helium self-trapping at high implantation rates and lower temperatures and one where helium–vacancy trapping dominates the helium cluster nucleation at lower implantation rates and higher temperatures. The transition between these regimes has been mapped as a function of implantation rate, temperature, and vacancy concentration and can provide guidance to understand the conditions under which neutron irradiation effects may contribute to subsurface gas nucleation in tungsten plasma-facing components.}, + number = {1}, + urldate = {2019-10-07}, + journal = {Fusion Science and Technology}, + author = {Yang, Zhangcan and Blondel, Sophie and Hammond, Karl D. and Wirth, Brian D.}, month = jan, - year = {2012}, - doi = {10.1016/B978-0-08-056033-5.00116-6}, - keywords = {Tritium, Hydrogen, Solubility, Diffusion, Fusion, Deuterium, Metals, Permeation, Structural materials, Carbides, Nitrides, Oxides, Barriers, First wall materials, Recombination}, - pages = {511--549}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Z3AYIJMQ\\B9780080560335001166.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QFUEQZ2R\\Causey et al. - 2012 - 4.16 - Tritium Barriers and Tritium Diffusion in F.pdf:application/pdf}, + year = {2017}, + keywords = {Monte Carlo}, + pages = {60--74}, } -@article{hurley_role_2016, - title = {Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600: {Study} coupling thermal desorption mass spectroscopy with numerical simulation}, - volume = {41}, - issn = {0360-3199}, - shorttitle = {Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600}, - url = {https://www.sciencedirect.com/science/article/pii/S0360319916300702}, - doi = {10.1016/j.ijhydene.2016.07.038}, - abstract = {The role grain boundaries play in the diffusion of hydrogen in polycrystalline alloys has long been debated. Some researchers have found that grain boundaries have an accelerating effect on the transport of hydrogen across a metal membrane, while others have stated this network of sites may slow the diffusion of hydrogen or have a mixed effect depending on grain size and orientation. Thermal desorption mass spectroscopy (TDS) was used to study the diffusion of deuterium, from 294 K to 550 K, in model single crystal and polycrystalline nickel base alloy, alloy 600, having a grain size of several tens of micrometers. Using a numerical routine, solving Fick's second law of diffusion, TDS spectra were fit or simulated. The derived diffusion constant parameters (D0 = (1.0 ± 0.5)·10−2 cm2 s−1 and ED = (45 ± 4) kJ mol−1) for the polycrystalline alloy adequately predict and simulate the deuterium desorption from the single crystal during TDS testing. Furthermore, in the temperature range and for the grain size studied no significant effect of grain boundaries on the diffusion of deuterium in alloy 600 was observed. Consequently, the measured diffusion parameters are representative of interstitial diffusion in the alloy.}, +@article{blondel_continuum-scale_2018, + title = {Continuum-scale modeling of helium bubble bursting under plasma-exposed tungsten surfaces}, + volume = {58}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/aae8ef}, + doi = {10.1088/1741-4326/aae8ef}, + abstract = {We present a comparison between a continuum-scale drift-diffusion-reaction cluster dynamics prediction of helium retention in low-energy helium plasma exposed tungsten and experimental measurements, in a temperature regime that did not produce tungsten fuzz. Our cluster dynamics model, Xolotl, has been successfully benchmarked to high helium implantation flux MD simulations at relatively low implanted fluence. In this article, we also describe the extension of the Xolotl DDR model to incorporate the effect of bubble bursting, which is observed in very high rate MD simulations, as well as MD simulations at longer times than simulated in our prior benchmarking comparison. The bursting model parameters have been tuned by comparing to MD simulations at a flux of 5.0 × 1027 m−2 s−1, and also compared to lower implanted fluence simulations performed at 4.0 × 1025 m−2 s−1. This article then reports on the consistency of the Xolotl predictions with respect to the size of the simulated cluster phase space (i.e. the maximum cluster size), initial vacancy concentration, and bubble growth trajectory (maximum number of helium atoms per vacancy). Finally, our simulation results are compared to helium plasma experiments that did not produce fuzz. While the Xolotl predictions including bubble bursting are in quantitative agreement with high-flux MD simulations, the initial comparison to plasma exposure experiments at a flux on the order of 1021 m−2 s−1 disagree by more than an order of magnitude, and in fact cannot reproduce the trends in helium retention with varying exposure temperature. Modifying the initial vacancy concentrations and helium cluster diffusion behavior in Xolotl leads to a reasonable agreement with the experimental observations, although the underlying physical explanation for these modifications remains unclear. The predicted helium content at experimentally relevant fluxes has been shown to be relatively insensitive to the parameters used in the bubble bursting model implemented in Xolotl, although these parameters have a larger influence at higher flux. More systematic comparisons between the modeling predictions with both experiments and MD simulation results is expected to improve the bubble bursting model in Xolotl in the future.}, language = {en}, - number = {38}, - urldate = {2022-02-04}, - journal = {International Journal of Hydrogen Energy}, - author = {Hurley, Caitlin and Martin, Frantz and Marchetti, Loïc and Chêne, Jacques and Blanc, Christine and Andrieu, Eric}, - month = oct, - year = {2016}, - keywords = {Grain boundaries, Hydrogen, Diffusion, Deuterium, Thermal desorption mass spectroscopy, Ni base alloy}, - pages = {17145--17153}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IWN8IM8S\\S0360319916300702.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5JERLF6X\\Hurley et al. - 2016 - Role of grain boundaries in the diffusion of hydro.pdf:application/pdf}, + number = {12}, + urldate = {2019-10-07}, + journal = {Nuclear Fusion}, + author = {Blondel, Sophie and Bernholdt, David E. and Hammond, Karl D. and Wirth, Brian D.}, + month = nov, + year = {2018}, + keywords = {Cluster dynamics}, + pages = {126034}, + file = {Blondel et al. - 2018 - Continuum-scale modeling of helium bubble bursting.pdf:D\:\\Logiciels\\data_zotero\\storage\\KSP2ZTJ8\\Blondel et al. - 2018 - Continuum-scale modeling of helium bubble bursting.pdf:application/pdf}, } -@article{zhang_diffusion_2020, - title = {Diffusion {Characterization} of {Hydrogen} {Isotopes} in {Hastelloy} {N} {Alloy} for the {Application} of {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} ({FHRs})}, - volume = {76}, +@article{blondel_benchmarks_2017, + title = {Benchmarks and {Tests} of a {Multidimensional} {Cluster} {Dynamics} {Model} of {Helium} {Implantation} in {Tungsten}}, + volume = {71}, issn = {1536-1055}, - url = {https://doi.org/10.1080/15361055.2020.1725368}, - doi = {10.1080/15361055.2020.1725368}, - abstract = {With the method of gas-driven permeation, a series of permeation experiments was carried out using Hastelloy N alloy membrane in an elevated temperature range of 400°C to 800°C with different hydrogen isotopes. A complete set of permeability, diffusivity, and Sieverts’ constant for hydrogen and deuterium in Hastelloy N alloy was successfully obtained. The isotope effect in the diffusion process was analyzed and compared with references. The ratios of diffusive transport parameters for hydrogen and deuterium were a permeability ratio of ФH/ФD = 1.32exp(0.34kJ/RT), a diffusivity ratio of DH/DD = 1.15exp(−0.41kJ/RT), and a Sieverts’ constant ratio of KS,H/KS,D = 1.16exp(0.21kJ/RT). The result that the permeation flux of deuterium was decreased after introducing hydrogen could be used to suppress the permeation of tritium in future tritium control of the Fluoride-salt-cooled High-temperature Reactor (FHR). Compared with NiO, the Cr2O3 formed in the surface oxidation layer of Hastelloy N alloy showed better hydrogen permeation barrier performance after baking above 700°C in air.}, - number = {4}, - urldate = {2022-02-04}, + url = {https://doi.org/10.13182/FST16-109}, + doi = {10.13182/FST16-109}, + abstract = {We present a hierarchical multiscale modeling study of implanted helium (He) segregation near grain boundaries (GBs) of tungsten. We extend our spatially dependent cluster dynamics model to two spatial dimensions in order to take into account the biased drift of mobile He clusters toward the GBs observed in atomic-scale simulations. We are able to reproduce the results from large-scale molecular dynamics simulations near and away from the GBs at low fluence with the extended cluster dynamics model. We suggest and verify that the sink (surface and GB) strengths are attenuated by the increasing concentration of He clusters at high fluence. This cluster dynamics model continues to set the stage for development of fully atomistically informed, coarse-grained models for computationally efficient predictions of He retention and surface morphological evolution, advancing progress toward the goal of efficient and optimal design of plasma-facing components.}, + number = {1}, + urldate = {2019-10-07}, journal = {Fusion Science and Technology}, - author = {Zhang, Dongxun and Liu, Wei and Liu, Wenguan}, - month = may, - year = {2020}, - note = {Publisher: Taylor \& Francis -\_eprint: https://doi.org/10.1080/15361055.2020.1725368}, - keywords = {fluoride salt, Hastelloy N alloy, permeation, surface oxidation}, - pages = {543--552}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\M5GTWE8E\\15361055.2020.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\L47DVY64\\Zhang et al. - 2020 - Diffusion Characterization of Hydrogen Isotopes in.pdf:application/pdf}, -} - -@article{diaz-rodriguez_direct_2022, - title = {Direct observation of hydrogen permeation through grain boundaries in tungsten}, - issn = {2522-574X}, - url = {https://doi.org/10.1007/s42247-021-00344-w}, - doi = {10.1007/s42247-021-00344-w}, - abstract = {In this paper, we report on an enhanced hydrogen permeation effect along grain boundaries in tungsten. Sputtered nanocolumnar tungsten layers (column lateral dimensions 100–150 nm and layer thickness 2 μm) were analysed by hydrogen permeation measurements in the temperature range 520–705 K. The experiments constitute a direct observation of this effect, previously postulated by means of a combination of indirect experiments and simulations and considered controversial due to the lack of direct measurements. DFT results support this observation since (i) the hydrogen binding energy to the grain boundary is 1.05 eV and (ii) the migration energies along the grain boundary and along the bulk are 0.12 eV and 0.20 eV, respectively. OKMC simulations, parametrized by DFT data, were used as a supporting tool to attain a better understanding of the involved phenomena. The OKMC results are also compatible with the observations. Indeed, they show that the fraction of hydrogen flux along grain boundaries in the steady-state permeation regime increases when decreasing the ratio of lateral dimensions to length of the nanocolumns, rapidly approaching unity when this ratio is {\textless} 2. Therefore, grain boundaries act as preferential migration pathways for H atoms at the studied temperature range in the studied samples. This behaviour has interesting implications to reduce the retention of hydrogen in several applications, in particular, fusion materials exposed to plasma discharges.}, - language = {en}, - urldate = {2022-01-31}, - journal = {Emergent Materials}, - author = {Díaz-Rodríguez, Pablo and Panizo-Laiz, Miguel and González, César and Iglesias, Roberto and Martín-Bragado, Ignacio and González-Arrabal, Raquel and Perlado, Jose Manuel and Peña-Rodríguez, Ovidio and Rivera, Antonio}, + author = {Blondel, Sophie and Bernholdt, David E. and Hammond, Karl D. and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, month = jan, - year = {2022}, - file = {Springer Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6JCI44VX\\Díaz-Rodríguez et al. - 2022 - Direct observation of hydrogen permeation through .pdf:application/pdf}, + year = {2017}, + keywords = {Cluster dynamics}, + pages = {84--92}, } -@article{van_den_kerkhof_impact_2021, - title = {Impact of {ELM} mitigation on the {ITER} monoblock thermal behavior and the tungsten recrystallization depth}, - volume = {27}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179121000867}, - doi = {10.1016/j.nme.2021.101009}, - abstract = {Type I Edge Localized Modes (ELMs) occur naturally in H-mode plasmas, the operational regime envisaged for ITER, and lead to high temporal heat load peaks on plasma-facing components that might induce surface melting and deteriorated material properties due to recrystallization. ELM mitigation techniques are being developed that either attempt to fully suppress the ELM, e.g. using resonant magnetic perturbations (RMP), or to trigger the ELM at higher frequencies, intending to reduce its energy content and hence the heat load peak. In this paper, the effect of the increased ELM frequency achieved by ELM mitigation techniques on the ITER tungsten divertor monoblock thermal and recrystallization behavior is numerically analyzed by solving the unsteady heat conduction equation when repeatedly exposing the monoblock to ELM-like heat loads under ITER baseline burning plasma operating conditions. The impinging heat load is based on a set of empirical relations readily found in literature and the recrystallization fraction is computed using an empirical data fit which is based on the non-isothermal JMAK equation as function of temperature and time. Uncertainties such as the statistical spread on empirical relations and the unknown inter-ELM heat load, as well as the effect of the ELM frequency, are quantified by a parameter scan. Adopting the recently developed concept of a ‘recrystallization budget’ to determine the allowed monoblock heat loads [G. De Temmerman et al., PPCF 60 (2018) 0044018], it was found that ELM frequencies between 25 – 50 Hz are allowed for inter-ELM heat loads between 9 – 6 MW m−2 , respectively, when assuming that the scaling for the peak ELM target energy density in [T. Eich et al., NME 12 (2017) 84-90] holds. This provides a new limit for ELM mitigation strategies in ITER.}, +@article{hammond_helium_2019, + title = {Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations}, + volume = {59}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab12f6}, + doi = {10.1088/1741-4326/ab12f6}, + abstract = {We investigate helium flux effects on helium transport and surface evolution in plasma-facing tungsten using molecular dynamics. The simulations span two orders of magnitude, from ITER-relevant levels to those more typical of simulations published to date. Simulation times of up to 2.5 µs (corresponding to actual fluences of m−2) are achieved, revealing concerted bubble-bursting events that are responsible for significant and very sudden changes in surface morphology. The depth distribution of helium depends very strongly on helium flux: helium self-trapping becomes more probable near the surface at high flux, and a layer of near-surface bubbles forms. Helium retention prior to the onset of bubble bursting is also substantially lower at low flux than it is at high flux. Surface features at low fluence are correlated with the positions of bubbles, but at high fluence, bubbles tend to coalesce, venting to the surface at one or more locations and leaving large interconnected cavities below the surface. Ruptured bubbles may serve as pathways deeper into the material, allowing helium to bypass the layer of near-surface bubbles and fill deeper, potentially much larger, bubbles that can produce more substantial surface features. Deeper bubbles also emit prismatic dislocation loops that can fill in cavities closer to the surface. Our results suggest that nearly all molecular dynamics simulations published to date are hampered by finite-size effects, and that helium flux is a very important parameter in determining the behavior of helium in plasma-facing components.}, language = {en}, - urldate = {2022-01-28}, - journal = {Nuclear Materials and Energy}, - author = {Van den Kerkhof, S. and Blommaert, M. and Pitts, R. A. and Dekeyser, W. and Carli, S. and Baelmans, M.}, - month = jun, - year = {2021}, - keywords = {ITER, Edge Localized Modes, ELM mitigation, Heat loads, Tungsten recrystallization}, - pages = {101009}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RZPFEKXI\\S2352179121000867.html:text/html}, + number = {6}, + urldate = {2019-10-25}, + journal = {Nuclear Fusion}, + author = {Hammond, Karl D. and Naeger, Ian V. and Widanagamaachchi, Wathsala and Lo, Li-Ta and Maroudas, Dimitrios and Wirth, Brian D.}, + month = may, + year = {2019}, + keywords = {Molecular Dynamics}, + pages = {066035}, + annote = { +He transport simulation with MD. +Simulation times up to 2.5 microseconds. +Investigation of helium flux influence on helium transport. +Creation of He bubbles and bursting. +Bursting only occurs at high fluences. +He self-trapping is more probable near the surface at high flux. +Bursting events are lees seeable if retention is plotted as function of fluence and not as function of time. +Large clusters are seeable at around 5/10 nm. +Lower fluxes mean deeper bubbles (but with a slower growth rate). +}, + file = {Hammond et al. - 2019 - Helium flux effects on bubble growth and surface m.pdf:D\:\\Logiciels\\data_zotero\\storage\\QZAGN88L\\Hammond et al. - 2019 - Helium flux effects on bubble growth and surface m.pdf:application/pdf}, } -@techreport{beck_research_1960, - title = {{RESEARCH} {AND} {DEVELOPMENT} {OF} {METAL} {HYDRIDES}. {Summary} {Report} for {October} 1, 1958-{September} 30, 1960}, - url = {https://www.osti.gov/biblio/4790244-research-development-metal-hydrides-summary-report-october-september}, - abstract = {A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding or controlling epithermal reactors. (auth)}, - language = {English}, - number = {LAR-10}, - urldate = {2022-01-26}, - institution = {Denver. Univ. Denver Research Inst.}, - author = {Beck, R. L.}, - month = nov, - year = {1960}, - doi = {10.2172/4790244}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EGU852SR\\Beck - 1960 - RESEARCH AND DEVELOPMENT OF METAL HYDRIDES. Summar.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XHU27Q9R\\4790244-research-development-metal-hydrides-summary-report-october-september.html:text/html}, +@article{boisse_modelling_2014, + series = {Proceedings of the 16th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-16)}, + title = {Modelling self trapping and trap mutation in tungsten using {DFT} and {Molecular} {Dynamics} with an empirical potential based on {DFT}}, + volume = {455}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514001032}, + doi = {10.1016/j.jnucmat.2014.02.031}, + abstract = {Density Functional Theory calculations and Molecular Dynamics with a recently developed potential for W–He were used to evaluate the thermal stability of helium–vacancy clusters (nHe.mv) as well as pure interstitial helium clusters in tungsten. The stability of such objects results from a competitive process between thermal emission of vacancies, self interstitial atoms (SIAs) and helium, depending on the helium-to-vacancy ratio in mixed clusters or helium number in pure interstitial helium clusters. We investigated in particular the thermodynamics and kinetics of self trapping and trap mutation, i.e. the emission of one SIA along with the creation of one vacancy from a vacancy–helium or pure helium object.}, + language = {en}, + number = {1}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Boisse, J. and Domain, C. and Becquart, C. S.}, + month = dec, + year = {2014}, + keywords = {Molecular Dynamics, Density Functional Theory}, + pages = {10--15}, + file = {Boisse et al. - 2014 - Modelling self trapping and trap mutation in tungs.pdf:D\:\\Logiciels\\data_zotero\\storage\\9D6A77RY\\Boisse et al. - 2014 - Modelling self trapping and trap mutation in tungs.pdf:application/pdf}, } -@article{segantin_exploration_2020, - title = {Exploration of power conversion thermodynamic cycles for {ARC} fusion reactor}, - volume = {155}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379620301939}, - doi = {10.1016/j.fusengdes.2020.111645}, - abstract = {In the worldwide energy industry, nuclear fusion could be a breakthrough in the medium-long term. One promising fusion machine under design at Massachusetts Institute of Technology is ARC reactor. It is likely that the first nuclear fusion plants will rely on a traditional thermodynamic cycle for the downstream power energy conversion. In this framework, one of the design aspects is to maximize the thermal efficiency. In the present paper the thermodynamic cycles, which could be adopted in ARC rector, are explored. Three cycles have been considered: the Rankine, the Brayton and a combined cycle. For the gas adopted in the Brayton and combined cycles, two options have been investigated: supercritical Helium and supercritical CO2. A comparison among thermal efficiency and preliminary considerations on component integrity’s, plant feasibility and economics of each studied configurations has been discussed to identify the possible best option for ARC reactor. The results show that a regenerative CO2 Brayton cycle with intercooler and re-heating systems is the most promising one. Such configurations is able to reach a thermodynamic efficiency of up to 0.6.}, +@article{lasa_md_2013, + series = {Proceedings of the 11th {Computer} {Simulation} of {Radiation} {Effects} in {Solids} ({COSIRES}) {Conference} {Santa} {Fe}, {New} {Mexico}, {USA}, {July} 24-29, 2012}, + title = {{MD} simulations of onset of tungsten fuzz formation under helium irradiation}, + volume = {303}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X12007719}, + doi = {10.1016/j.nimb.2012.11.029}, + abstract = {When helium (He) escapes a fusion reactor plasma, a tungsten (W)-based divertor may, under some conditions, form a fuzz-like nano-morphology. This is a highly undesired phenomenon for the divertor, and is not well understood. We performed molecular dynamics simulations of high fluence He and also C-seeded He (He+C) irradiation on W, focusing on the effect of the high fluence, the temperature and the impurities on the onset of the structure formation. We concluded that MD reproduces the experimentally found square root of time dependence of the surface growth. The He atomic density decreases when increasing the number of He atoms in the cell. A higher temperature causes a larger bubble growth and desorption activity, specially for the pure He irradiation cases. It also it leads to W recrystallization for the He+C irradiation cases. Carbon acts as a local He trap for small clusters or single atoms and causes a larger loss of crystallinity of the W surface.}, language = {en}, - urldate = {2022-01-26}, - journal = {Fusion Engineering and Design}, - author = {Segantin, Stefano and Bersano, Andrea and Falcone, Nicolò and Testoni, Raffaella}, - month = jun, - year = {2020}, - keywords = {ARC, Balance of plant, Nuclear reactors, Power conversion, Thermodynamic cycles, Thermodynamic efficiency}, - pages = {111645}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JJWLYNL5\\S0920379620301939.html:text/html}, + urldate = {2019-10-30}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Lasa, A. and Henriksson, K. O. E. and Nordlund, K.}, + month = may, + year = {2013}, + keywords = {Molecular Dynamics, Bubble}, + pages = {156--161}, + file = {Lasa et al. - 2013 - MD simulations of onset of tungsten fuzz formation.pdf:D\:\\Logiciels\\data_zotero\\storage\\GVK3G6XA\\Lasa et al. - 2013 - MD simulations of onset of tungsten fuzz formation.pdf:application/pdf}, } -@phdthesis{mangiarotti_design_2016, - type = {Thesis}, - title = {Design of demountable toroidal field coils with {REBCO} superconductors for a fusion reactor}, - copyright = {M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.}, - url = {https://dspace.mit.edu/handle/1721.1/103659}, - abstract = {The recent development of REBCO superconducting tapes, cabling methods and joint concepts could be a revolutionary development for magnetic fusion. REBCO has significantly better performance at high magnetic fields than traditional low temperature superconductors (LTS), and can be operated at a higher temperature than LTS for reduced thermodynamic cost of cooling. Use of REBCO superconductors in the magnet systems of tokamaks allows building demountable toroidal field (TF) coils, greatly simplifying reactor construction and maintenance. A demountable TF coil system with REBCO superconductors for a fusion reactor has been conceptually designed. The coil system operates at 20 K, with a maximum magnetic field of 20 T. The magnets are divided into two coil segments and can be detached and remounted to allow the internal components of the reactor to be removed vertically as one piece. Operating at 20 T and 20 K, the stress in most of the coils is acceptable (less than 2/3 the yield strength and less than 1/2 the ultimate tensile strength of the structural materials). The strain in the superconductors is lower than the reversible degradation limit. The electrical resistance in each conductor joint is 10 n [Omega]. The total heat generation in the reactor superconducting TF magnets is approximately 1.9 MW, of which about 25 \% is nuclear heating and 75 \% joint heating. 71 MW of electricity are required for cooling the coils at 20 K, about 7 \% of the electric energy the reactor generates. The expected time to warm-up the magnets from the operation temperature to room temperature is 7 days, and approximately the same for cool-down back to the operation temperature. The analysis of the conceptual magnet design is encouraging, as no insuperable problems have been identified. This conceptual design can be used as a starting point for a full engineering design of demountable fusion reactors magnets.}, - language = {eng}, - urldate = {2022-01-26}, - school = {Massachusetts Institute of Technology}, - author = {Mangiarotti, Franco Julio}, - year = {2016}, - note = {Accepted: 2016-07-18T19:10:37Z}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BIUNBG5Q\\Mangiarotti - 2016 - Design of demountable toroidal field coils with RE.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TWISVT2V\\103659.html:text/html}, +@article{sandoval_overview_2019, + title = {An {Overview} of {Recent} {Standard} and {Accelerated} {Molecular} {Dynamics} {Simulations} of {Helium} {Behavior} in {Tungsten}}, + volume = {12}, + issn = {1996-1944}, + url = {https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6721179/}, + doi = {10.3390/ma12162500}, + abstract = {One of the most critical challenges for the successful adoption of nuclear fusion power corresponds to plasma-facing materials. Due to its favorable properties in this context (low sputtering yield, high thermal conductivity, high melting point, among others), tungsten is a leading candidate material. Nevertheless, tungsten is affected by the plasma and fusion byproducts. Irradiation by helium nuclei, in particular, strongly modifies the surface structure by a synergy of processes, whose origin is the nucleation and growth of helium bubbles. In this review, we present recent advances in the understanding of helium effects in tungsten from a simulational approach based on accelerated molecular dynamics, which emphasizes the use of realistic parameters, as are expected in experimental and operational fusion power conditions.}, + number = {16}, + urldate = {2019-10-28}, + journal = {Materials}, + author = {Sandoval, Luis and Perez, Danny and Uberuaga, Blas P. and Voter, Arthur F.}, + month = aug, + year = {2019}, + pmid = {31394714}, + pmcid = {PMC6721179}, + keywords = {Molecular Dynamics}, + file = {Sandoval et al. - 2019 - An Overview of Recent Standard and Accelerated Mol.pdf:D\:\\Logiciels\\data_zotero\\storage\\9M2CDM2D\\Sandoval et al. - 2019 - An Overview of Recent Standard and Accelerated Mol.pdf:application/pdf}, } -@article{creely_overview_2020, - title = {Overview of the {SPARC} tokamak}, - volume = {86}, - issn = {0022-3778, 1469-7807}, - url = {https://www.cambridge.org/core/journals/journal-of-plasma-physics/article/overview-of-the-sparc-tokamak/DD3C44ECD26F5EACC554811764EF9FF0}, - doi = {10.1017/S0022377820001257}, - abstract = {The SPARC tokamak is a critical next step towards commercial fusion energy. SPARC is designed as a high-field (B0=12.2B0=12.2B\_0 = 12.2 T), compact (R0=1.85R0=1.85R\_0 = 1.85 m, a=0.57a=0.57a = 0.57 m), superconducting, D-T tokamak with the goal of producing fusion gain Q{\textgreater}2Q{\textgreater}2Q{\textgreater}2 from a magnetically confined fusion plasma for the first time. Currently under design, SPARC will continue the high-field path of the Alcator series of tokamaks, utilizing new magnets based on rare earth barium copper oxide high-temperature superconductors to achieve high performance in a compact device. The goal of Q{\textgreater}2Q{\textgreater}2Q{\textgreater}2 is achievable with conservative physics assumptions (H98,y2=0.7H98,y2=0.7H\_\{98,y2\} = 0.7) and, with the nominal assumption of H98,y2=1H98,y2=1H\_\{98,y2\} = 1, SPARC is projected to attain Q≈11Q≈11Q {\textbackslash}approx 11 and Pfusion≈140Pfusion≈140P\_\{{\textbackslash}textrm \{fusion\}\} {\textbackslash}approx 140 MW. SPARC will therefore constitute a unique platform for burning plasma physics research with high density (⟨ne⟩≈3×1020 m−3⟨ne⟩≈3×1020 m−3{\textbackslash}langle n\_\{e\} {\textbackslash}rangle {\textbackslash}approx 3 {\textbackslash}times 10{\textasciicircum}\{20\}{\textbackslash} {\textbackslash}textrm \{m\}{\textasciicircum}\{-3\}), high temperature (⟨Te⟩≈7⟨Te⟩≈7{\textbackslash}langle T\_e {\textbackslash}rangle {\textbackslash}approx 7 keV) and high power density (Pfusion/Vplasma≈7 MWm−3Pfusion/Vplasma≈7 MWm−3P\_\{{\textbackslash}textrm \{fusion\}\}/V\_\{{\textbackslash}textrm \{plasma\}\} {\textbackslash}approx 7{\textbackslash} {\textbackslash}textrm \{MW\}{\textbackslash},{\textbackslash}textrm \{m\}{\textasciicircum}\{-3\}) relevant to fusion power plants. SPARC's place in the path to commercial fusion energy, its parameters and the current status of SPARC design work are presented. This work also describes the basis for global performance projections and summarizes some of the physics analysis that is presented in greater detail in the companion articles of this collection.}, +@article{jourdan_variable-gap_2011, + title = {A variable-gap model for calculating free energies of helium bubbles in metals}, + volume = {418}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311511006921}, + doi = {10.1016/j.jnucmat.2011.07.019}, + abstract = {We propose a variable-gap energy model for helium bubbles in metals, based on molecular dynamics (MD) calculations. The emphasis is put on the appropriate description of the helium-metal repulsion, which can be modelled as a variable-size gap between regions occupied by helium and metal atoms. Each contribution to the bubble energy is parametrized on MD calculations performed in iron. The model is shown to reproduce accurately the dissociation energies obtained by MD over a large range of helium-to-vacancy ratios. Improvements over previous models are shown on a few equilibrium properties: binding energies, solid to fluid transition, helium density in bubbles and validity of Laplace law. Beyond the iron case, such a model should be valid in other metals where helium behavior is similar.}, language = {en}, - number = {5}, - urldate = {2022-01-26}, - journal = {Journal of Plasma Physics}, - author = {Creely, A. J. and Greenwald, M. J. and Ballinger, S. B. and Brunner, D. and Canik, J. and Doody, J. and Fülöp, T. and Garnier, D. T. and Granetz, R. and Gray, T. K. and Holland, C. and Howard, N. T. and Hughes, J. W. and Irby, J. H. and Izzo, V. A. and Kramer, G. J. and Kuang, A. Q. and LaBombard, B. and Lin, Y. and Lipschultz, B. and Logan, N. C. and Lore, J. D. and Marmar, E. S. and Montes, K. and Mumgaard, R. T. and Paz-Soldan, C. and Rea, C. and Reinke, M. L. and Rodriguez-Fernandez, P. and Särkimäki, K. and Sciortino, F. and Scott, S. D. and Snicker, A. and Snyder, P. B. and Sorbom, B. N. and Sweeney, R. and Tinguely, R. A. and Tolman, E. A. and Umansky, M. and Vallhagen, O. and Varje, J. and Whyte, D. G. and Wright, J. C. and Wukitch, S. J. and Zhu, J. and Team, the SPARC}, - month = oct, - year = {2020}, - note = {Publisher: Cambridge University Press}, - keywords = {fusion plasma, plasma devices, plasma confinement}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A9A42L5X\\DD3C44ECD26F5EACC554811764EF9FF0.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WPBNM33F\\Creely et al. - 2020 - Overview of the SPARC tokamak.pdf:application/pdf}, -} - -@article{zeng_development_2018, - title = {Development of the {Tritium} {Transport} {Analysis} {Code} for the {Thorium}-{Based} {Molten} {Salt} {Reactor}}, - volume = {203}, - issn = {0029-5450}, - url = {https://doi.org/10.1080/00295450.2018.1433408}, - doi = {10.1080/00295450.2018.1433408}, - abstract = {The Thorium-Based Molten Salt Reactor (TMSR) has been highlighted for its safety, economy, and nuclear nonproliferation. A program for developing the TMSR system has been launched in Shanghai Institute of Applied Physics, Chinese Academy of Sciences. In the TMSR system, mixtures of LiF and BeF2, termed FLiBe, are proposed and used as the primary coolant salt, in which tritium is produced mainly by the neutron reactions of lithium. In the TMSR system, at high temperatures, tritium can permeate through metal walls to the surroundings, leading to a potential radiological hazard. Thus, tritium control becomes a major problem hindering the development of the TMSR system. Evaluation of the tritium distribution is necessary for tritium control in the TMSR system. In this study, the Tritium Transport Analysis Code (TTAC) has been developed for simulating the tritium behaviors in the TMSR system (hence, the code TMSR-TTAC), such as tritium chemical forms in coolant salts, tritium transport behaviors, and tritium distribution in the system. The model code is developed by the MATLAB/SIMULINK package, and it is based on the mass balance equations of the tritium-containing species and hydrogen. TMSR-TTAC is benchmarked with the molten salt reactor model, which is based on Molten Salt Reactor Experiment designs. The results show that TMSR-TTAC has the ability to calculate the tritium distribution in the TMSR system.}, number = {1}, - urldate = {2022-01-24}, - journal = {Nuclear Technology}, - author = {Zeng, Youshi and Wu, Shengwei and Liu, Wei and Wang, Guanghua and Qian, Nan and Wu, Xiaoling and Liu, Wenguan and Huang, Yu and Qian, Yuan}, - month = jul, - year = {2018}, - note = {Publisher: Taylor \& Francis -\_eprint: https://doi.org/10.1080/00295450.2018.1433408}, - keywords = {Thorium-based molten salt reactor, tritium distribution, tritium transport}, - pages = {48--57}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\T5RKNWYJ\\00295450.2018.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DMS6YA55\\Zeng et al. - 2018 - Development of the Tritium Transport Analysis Code.pdf:application/pdf}, + urldate = {2019-11-05}, + journal = {Journal of Nuclear Materials}, + author = {Jourdan, T. and Crocombette, J. -P.}, + month = nov, + year = {2011}, + keywords = {Molecular Dynamics, Bubble}, + pages = {98--105}, + file = {Jourdan et Crocombette - 2011 - A variable-gap model for calculating free energies.pdf:D\:\\Logiciels\\data_zotero\\storage\\PWAI98VP\\Jourdan et Crocombette - 2011 - A variable-gap model for calculating free energies.pdf:application/pdf}, } -@article{nakamura_hydrogen_2015, - title = {Hydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket}, - abstract = {Mixed fluoride molten salts Flinak (LiF+NaF+KF) and Flibe (LiF+BeF2) are expected to work as a tritium breeder in a fusion reactor blanket along with coolant and uranium fuel dissolver in a molten salt fission reactor. In this study, after making the molten salts in an electric furnace and purifying the salts by HF, experiments were performed to determine the behavior of H2 permeation through the fluoride molten salts at static conditions in the range of 500-600 °C using an apparatus composed of tertiary cylindrical Monel400 tubes. In addition, transient H2 diffusion equations in molten salts were solved, and results were compared with experimental effluent H2 concentration curves. It is proved experimentally that the H2 permeability through Flibe or Flinak has linear pressure dependence, and permeability, diffusivity and solubility of H2 in the fluoride molten salts are correlated to their respective Arrhenius-type equations.}, +@article{wurger_is_2013, + series = {10th {International} {Meeting} on {Thermodiffusion}}, + title = {Is {Soret} equilibrium a non-equilibrium effect?}, + volume = {341}, + issn = {1631-0721}, + url = {http://www.sciencedirect.com/science/article/pii/S1631072113000417}, + doi = {10.1016/j.crme.2013.02.006}, + abstract = {Recent thermophoretic experiments on colloidal suspensions revived an old debate, namely whether the Soret effect is properly described by thermostatics, or necessarily requires non-equilibrium thermodynamics. Based on colloidal transport theory and the entropy production of the related viscous flow, our analysis leads to the conclusion that the equilibrium approach may work for small ions, yet fails for colloidal particles and polymers. Regarding binary molecular mixtures, our results shed some doubt on the validity of thermostatic approaches that derive the Soret coefficient from equilibrium potentials.}, language = {en}, - author = {Nakamura, Akira and Fukada, Satoshi and Nishiumi, Ryosuke}, - year = {2015}, - pages = {5}, - file = {Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RN3G2BNI\\Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:application/pdf;Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BKLAAYU5\\Nakamura et al. - Hydrogen isotopes permeation in a fluoride molten .pdf:application/pdf}, + number = {4}, + urldate = {2019-10-17}, + journal = {Comptes Rendus Mécanique}, + author = {Würger, Alois}, + month = apr, + year = {2013}, + pages = {438--448}, + file = {Würger - 2013 - Is Soret equilibrium a non-equilibrium effect.pdf:D\:\\Logiciels\\data_zotero\\storage\\MH859YQX\\Würger - 2013 - Is Soret equilibrium a non-equilibrium effect.pdf:application/pdf}, } -@article{rader_verification_2018, - title = {Verification of {Modelica}-{Based} {Models} with {Analytical} {Solutions} for {Tritium} {Diffusion}}, - volume = {203}, - issn = {0029-5450, 1943-7471}, - url = {https://www.tandfonline.com/doi/full/10.1080/00295450.2018.1431505}, - doi = {10.1080/00295450.2018.1431505}, - abstract = {Tritium transport in metal and molten salt fluids combined with diffusion through high-temperature structural materials is an important phenomenon in both magnetic confinement fusion (MCF) and molten salt reactor (MSR) applications. For MCF, tritium is desirable to capture for fusion fuel. For MSRs, uncaptured tritium potentially can be released to the environment. In either application, quantifying the time- and space-dependent tritium concentration in the working fluid(s) and structural components is necessary.}, +@article{sefta_helium_2013, + title = {Helium bubble bursting in tungsten}, + volume = {114}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.4860315}, + doi = {10.1063/1.4860315}, + number = {24}, + urldate = {2019-10-25}, + journal = {Journal of Applied Physics}, + author = {Sefta, Faiza and Juslin, Niklas and Wirth, Brian D.}, + month = dec, + year = {2013}, + keywords = {Bursting, Bubble}, + pages = {243518}, +} + +@article{miyamoto_microscopic_2011, + series = {Proceedings of the 19th {International} {Conference} on {Plasma}-{Surface} {Interactions} in {Controlled} {Fusion}}, + title = {Microscopic damage of tungsten exposed to deuterium–helium mixture plasma in {PISCES} and its impacts on retention property}, + volume = {415}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311511000201}, + doi = {10.1016/j.jnucmat.2011.01.008}, + abstract = {Microscopic damage and D retention in tungsten have been investigated for low-energy (∼60–120eV), high flux (∼1022m−2s−1), high fluence (∼5×1025m−2) ion bombardment at moderate temperature (∼573–773K) in mixed species D+He plasmas in the linear divertor plasma simulators PISCES-A and B. A significant reduction in D retention a +nd the formation of nanometer-sized He bubbles occur in W due to seeding of He into the D plasma. The volume fraction of He bubbles, estimated with TEM observations and ellipsometric measurements, exceeds the percolation threshold. The desorption mechanism that injected D atoms diffuse back to the surface through the percolating bubbles is suggested. The seeding of Be into D+He mixture plasma eliminates this He effect on the reduction in D retention.}, language = {en}, - number = {1}, - urldate = {2022-01-24}, - journal = {Nuclear Technology}, - author = {Rader, Jordan D. and Greenwood, M. Scott and Humrickhouse, Paul W.}, - month = jul, - year = {2018}, - pages = {58--65}, - file = {Rader et al. - 2018 - Verification of Modelica-Based Models with Analyti.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\49SLH59B\\Rader et al. - 2018 - Verification of Modelica-Based Models with Analyti.pdf:application/pdf}, + number = {1, Supplement}, + urldate = {2019-10-25}, + journal = {Journal of Nuclear Materials}, + author = {Miyamoto, M. and Nishijima, D. and Baldwin, M. J. and Doerner, R. P. and Ueda, Y. and Yasunaga, K. and Yoshida, N. and Ono, K.}, + month = aug, + year = {2011}, + keywords = {Experiment, Bubble}, + pages = {S657--S660}, + file = {Miyamoto et al. - 2011 - Microscopic damage of tungsten exposed to deuteriu.pdf:D\:\\Logiciels\\data_zotero\\storage\\W3P23H4A\\Miyamoto et al. - 2011 - Microscopic damage of tungsten exposed to deuteriu.pdf:application/pdf}, } -@article{merrill_modifications_2019, - series = {{SI}:{SOFT}-30}, - title = {Modifications to the {MELCOR}-{TMAP} code to simultaneously treat multiple fusion coolants}, - volume = {146}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379618308135}, - doi = {10.1016/j.fusengdes.2018.12.048}, - abstract = {This paper describes recent progress at Idaho National Laboratory (INL) in developing the MELCOR-TMAP computer code for fusion. The MELCOR-TMAP for fusion computer code is being developed by INL’s Fusion Safety Program (FSP) by modifying the US Nuclear Regulatory Commission’s (NRC’s) MELCOR computer code for fission reactor severe accident analyses. Recently the INL FSP completed the process of merging INL’s Tritium Migration Analysis Program (TMAP) with MELCOR to provide the US fusion community with a more comprehensive tool for analyzing accidents in future fusion reactors. However, prior to the present modifications, a MELCOR-TMAP user could only substitute one of a number of available fusion coolants for MELCOR’s default coolant of water. This new capability corrects this modeling gap needed for safety assessments of fusion reactors that contain more than a single coolant. In this article, we discuss the present code modifications, benchmark MELCOR-TMAP against predictions from previous versions of the MELCOR code, illustrate the application of the code to analysis of an accident in a multiple fluids reactor concept, and describe future plans for the MELCOR-TMAP code.}, +@article{zhou_towards_2010, + title = {Towards suppressing {H} blistering by investigating the physical origin of the {H}–{He} interaction in {W}}, + volume = {50}, + issn = {0029-5515}, + doi = {10.1088/0029-5515/50/11/115010}, + abstract = {We investigate the physical origin of H–He interaction in W in terms of optimal charge density by calculating the energetics and diffusion properties using a first-principles method. On the one hand, we show a strong attraction between H and He in W originated from the charge density redistribution due to the presence of He, driving H segregation towards He. This can block the permeation of H into deeper bulk and thus suppress H blistering. On the other hand, we demonstrate that He, rather than H, energetically prefers to occupy the vacancy centre due to its closed-shell structure, which can block H2 formation at the vacancy centre. This is because He causes a redistribution of charge density inside the vacancy to make it ‘not optimal’ for the formation of H2 molecules, which can be treated as a preliminary nucleation of the H bubbles. We thus propose that H retention and blistering in W can be suppressed by doping the noble gas elements.}, language = {en}, - urldate = {2022-01-24}, - journal = {Fusion Engineering and Design}, - author = {Merrill, B. J. and Humrickhouse, P. W. and Yoon, S-J.}, - month = sep, - year = {2019}, - keywords = {Tritium transport, Accident analyses, Fusion safety, MELCOR, TMAP}, - pages = {289--292}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2BISI243\\S0920379618308135.html:text/html}, + number = {11}, + journal = {Nuclear Fusion}, + author = {Zhou, Hong-Bo and Liu, Yue-Lin and Jin, Shuo and Zhang, Ying and Luo, G.-N. and Lu, Guang-Hong}, + month = oct, + year = {2010}, + keywords = {Blistering, Density Functional Theory, Bubble}, + pages = {115010}, + file = {Zhou et al. - 2010 - Towards suppressing H blistering by investigating .pdf:D\:\\Logiciels\\data_zotero\\storage\\X29IENDC\\Zhou et al. - 2010 - Towards suppressing H blistering by investigating .pdf:application/pdf}, } -@techreport{fuerst_tritium_2021, - title = {Tritium {Transport} {Phenomena} in {Molten}-{Salt} {Reactors}: {Molten} {Salt} {Tritium} {Transport} {Experiment} {Design}}, - shorttitle = {Tritium {Transport} {Phenomena} in {Molten}-{Salt} {Reactors}}, - url = {https://www.osti.gov/biblio/1828384}, - abstract = {Tritium is produced from neutron interactions with both lithium and beryllium. Large quantities of tritium are generated in Molten Salt Reactors (MSRs) which use LiF/BeF2 (FLiBe) as the fuel salt. Tritium is unique among the radionuclide hazards as it readily permeates through metal structural materials at high temperatures. All metal surfaces are potential release paths for tritium. For adequate safety analysis and eventual licensing of new reactors, predictive models for tritium transport and release from MSRs must be developed. These models must account for the multiple transport phenomena involved with tritium: fuel salt phase mass transport, dissociation/recombination reactions on metal surfaces, interstitial diffusion through the metal structure, and salt or gas phase mass transport in the downstream fluid. These models also must also be validated with representative experiments. Our previous report outlined tritium transport phenomena involved in MSRs, made suggestions on gaps in the transport dataset, and proposed an experimental test stand to test combined transport effects – tritium transport through pipe walls in a convective salt flow. In this report, we summarize an updated analysis framework for tritium transport in MSRs, report our results on hydrogen and deuterium permeation through Hastelloy N, and describe the final design of the Molten Salt Tritium Transport Experiment (MSTTE, pronounced “misty”). The MSRE provides the only wholistic experimental data set for tritium transport in MSRs and understanding the transport phenomena involved in the MSRE is crucial for future model development. One set of parameters in our analysis framework was unknown for the MSRE—surface reaction rates for tritium on Hastelloy N. This warranted our hydrogen and deuterium permeation campaign to assess the permeability, diffusivity, and solubility of hydrogen isotopes in clean Hastelloy N. Surface reaction rate constants were probed by low pressure measurements, however, no surface effects were observed in the limits of our permeation apparatus. Permeation experiments on oxidized Hastelloy N were not performed for this report but are planned in future work. The experimental test stand, MSTTE, measures combined transport properties of the salt-metal system. MSTTE is a forced convection FLiBe loop with custom designed test section to measure tritium transport through candidate structural materials. We use MSRE relevant dimensionless numbers to design and scale the test section. Hastelloy N is a candidate loop and test section material due to the relevance for the MSRE and related designs, however, other metals are being considered (e.g. 316H SS) which may better align with current vendor concepts.}, - language = {English}, - number = {INL/EXT-21-63108-Rev000}, - urldate = {2022-01-24}, - institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)}, - author = {Fuerst, Thomas F. and Taylor, Chase N. and Humrickhouse, Paul W.}, - month = jun, - year = {2021}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DNQNXCCV\\Fuerst et al. - 2021 - Tritium Transport Phenomena in Molten-Salt Reactor.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XNB6IJYL\\1828384.html:text/html}, +@article{morishita_nucleation_2007, + title = {Nucleation path of helium bubbles in metals during irradiation}, + volume = {87}, + issn = {1478-6435}, + url = {https://doi.org/10.1080/14786430601096910}, + doi = {10.1080/14786430601096910}, + abstract = {A thermodynamic formalization is developed for description of the nucleation and growth of helium bubbles in metals during irradiation. The proposed formalization is available for evaluating both microstructural changes in fusion first wall materials where helium is produced by (n, α) nuclear transmutation reactions, and those in fusion diverter materials where helium particles with low energy are directly implanted. The calculated nucleation barrier is significantly reduced by the presence of helium, showing that a helium bubble with an appropriate number of helium atoms depending on bubble size can nucleate without any large nucleation barriers, even at a condition where an empty void has very large nucleation barriers without helium. With the proposed thermodynamic formalization, the nucleation and growth process of helium bubbles in iron during irradiation is simulated by the kinetic Monte Carlo (KMC) technique. It shows the nucleation path of a helium bubble on the (N He, N V) space as functions of temperatures and the concentration of helium in the matrix, where N He and N V are the numbers of helium atoms and vacancies contained in the helium bubble, respectively. Bubble growth rates depend on the nucleation path and suggest that two different mechanisms operate for bubble growth: one is controlled by vacancy diffusion and the other is controlled by interstitial helium diffusion.}, + number = {7}, + urldate = {2019-10-31}, + journal = {Philosophical Magazine}, + author = {Morishita, K.}, + month = mar, + year = {2007}, + keywords = {Bubble, Monte Carlo}, + pages = {1139--1158}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\Y792FZS8\\Morishita - 2007 - Nucleation path of helium bubbles in metals during.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\68FG98DG\\14786430601096910.html:text/html}, } -@article{woller_impact_2017, - title = {Impact of helium ion energy modulation on tungsten surface morphology and nano-tendril growth}, - volume = {57}, - issn = {0029-5515, 1741-4326}, - url = {https://iopscience.iop.org/article/10.1088/1741-4326/aa67ac}, - doi = {10.1088/1741-4326/aa67ac}, - abstract = {Time-modulated helium (He) ion energy (e.g. VBias  =  −50  +  25·sin(2πfRF · t), fRF  =  13.56 MHz) is demonstrated to strongly affect the development of tungsten (W) surface morphology that results from He plasma irradiation in the DIONISOS linear plasma experiment. Nano-tendril bundles (NTBs), which appear as isolated ‘islands’ of nano-tendrils, can rapidly grow on an otherwise smooth W surface. This is in contrast to previously seen full-surface coverage of nano-tendril growth known as ‘fuzz’. When tall NTBs form, less than 15\% of the surface contains nano-tendrils. The NTB surface coverage changes with growth conditions and the total volume of nano-tendrils in the NTBs is observed to be up to a factor of 16 larger than when fuzz is grown. This indicates that long-range W surface transport underlies nano-tendril formation. Surface temperature 870–1220 K, the DC bias potential  −30 to  −70 V, and the ion flux density 4.4  ×  1021–1.1  ×  1022 He · m−2 · s−1 are varied in the experiments. NTBs form at similar conditions as fuzz with the critical difference being the RF modulation of the ion energy bombarding the W, another indication of the importance of W surface transport. Mass loss measurements indicate net erosion with a yield of 1–8  ×  10−4 W/He when NTBs form; erosion that is not attributable to chemical or physical sputtering by He or impurities in the plasma. The erosion is correlated to the NTB growth, based on post-exposure inspection by electron microscopy indicating that NTBs are prone to loss from the surface. NTB growth is compared to the empirical growth-erosion model of fuzz, showing NTBs grow up to a factor of 100 times taller than the expected fuzz layer depth under DC bias conditions. Insights into nano-tendril growth provided by this new growth regime are discussed. Strategies to mitigate W fuzz growth may inadvertently result in rapid localized nano-tendril bundle growth with a higher probability of dust production.}, +@article{myers_ion_1985, + series = {Proceedings of the {International} {Conference} on {Surface} {Modification} of {Metals} by {Ion} {Beams}}, + title = {Ion beam studies of hydrogen in metals}, + volume = {69}, + issn = {0025-5416}, + url = {http://www.sciencedirect.com/science/article/pii/0025541685903398}, + doi = {10.1016/0025-5416(85)90339-8}, + abstract = {Methods based on ion implantation and nuclear reaction analysis have been developed and used to investigate fundamental aspects of the behavior of hydrogen isotopes in metals. The binding enthalpy of deuterium at irradiation defects, helium bubbles, deuterium bubbles and metal-oxide interfaces was measured for aluminum, iron, nickel, copper, palladium, austenitic stainless steel, Inconel and amorphous Fe40Ni40P14B6. The binding enthalpies determined for the pure metals are in excellent agreement with mechanistic calculations based on effective medium theory and other information. Surface-limited release of deuterium from iron, stainless steel and Inconel was measured as a function of temperature and the state of surface oxidation. The release rate was accurately proportional to the square of the deuterium concentration in solution, permitting the results to be expressed in terms of a surface recombination coefficient. This quantity was up to four orders of magnitude greater for an ion-sputtered surface than for a surface with electropolish oxide. The diffusion coefficient and solid solubility of tritium in stainless steel were measured for the first time at the ice point, thereby extending downward by three orders of magnitude the diffusivities available from conventional permeation experiments. Deuterium concentration profiles resulting from electrochemical charging of Incology 903 were measured as a function of charging current, thereby providing a direct systematic calibration of such charging in an austenitic material where conventional permeation measurements are precluded by the small hydrogen diffusion rate.}, language = {en}, - number = {6}, - urldate = {2022-01-24}, - journal = {Nuclear Fusion}, - author = {Woller, K.B. and Whyte, D.G. and Wright, G.M.}, - month = jun, - year = {2017}, - pages = {066005}, - file = {Woller et al. - 2017 - Impact of helium ion energy modulation on tungsten.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7MH548QA\\Woller et al. - 2017 - Impact of helium ion energy modulation on tungsten.pdf:application/pdf}, + number = {2}, + urldate = {2019-11-05}, + journal = {Materials Science and Engineering}, + author = {Myers, S. M. and Wampler, W. R. and Besenbacher, F. and Robinson, S. L. and Moody, N. R.}, + month = mar, + year = {1985}, + keywords = {Experiment}, + pages = {397--409}, + annote = { +This paper shows measured and predicted values for binding energies of H atoms with several types of defects in different materials (W is not studied). +  +}, + file = {Myers et al. - 1985 - Ion beam studies of hydrogen in metals.pdf:D\:\\Logiciels\\data_zotero\\storage\\EC7QR6UK\\Myers et al. - 1985 - Ion beam studies of hydrogen in metals.pdf:application/pdf}, } -@article{raiman_corrosion_2022, - title = {Corrosion of {316H} stainless steel in flowing {FLiNaK} salt}, - volume = {561}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311522000472}, - doi = {10.1016/j.jnucmat.2022.153551}, - abstract = {Type 316H stainless steel samples were exposed to flowing FLiNaK salt for 1000 h in a monometallic thermal convection loop (TCL) with a maximum temperature of 650 °C and a minimum of 540 °C. Samples in the hottest part of the TCL lost mass, with a maximum mass loss of 1.4 mg/cm2, while samples in the coldest parts of the TCL gained mass, with a maximum mass gain of 1.0 mg/cm2. Analysis of the samples that gained mass showed an Fe-rich layer on the sample surfaces, indicating that Fe, not Cr, was the primary deposition product in the TCL. Cr loss was apparent to a depth of ∼5 µm in the hot leg. Post-exposure analysis of the salt showed major increases in the Cr, Fe, and Mn contents. The TCL was modeled using the TRANSFORM code. Modeled values matched the experimental temperature measurements showing that TRANSFORM is capable of accurately simulating the TCL conditions.}, - language = {en}, - urldate = {2022-01-23}, - journal = {Journal of Nuclear Materials}, - author = {Raiman, Stephen S. and Kurley, J. Matthew and Sulejmanovic, Dino and Willoughby, Adam and Nelson, Scott and Mao, Keyou and Parish, Chad M. and Greenwood, M. Scott and Pint, Bruce A.}, - month = apr, - year = {2022}, - keywords = {Corrosion, Molten salt, Molten salt reactor, MSR, Fluoride Salt, Stainless steel}, - pages = {153551}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PV2I3U2I\\S0022311522000472.html:text/html}, +@article{henriksson_depths_2006, + title = {The {Depths} of {Hydrogen} and {Helium} {Bubbles} in {Tungsten}: {A} {Comparison}}, + volume = {50}, + issn = {1536-1055}, + shorttitle = {The {Depths} of {Hydrogen} and {Helium} {Bubbles} in {Tungsten}}, + url = {https://doi.org/10.13182/FST06-A1219}, + doi = {10.13182/FST06-A1219}, + abstract = {The role of self-trapping and defect trapping of hydrogen and helium implanted into tungsten has been investigated using density functional theory (DFT) calculations, molecular dynamics simulations, and kinetic Monte Carlo simulations (KMCSs). The potential energy curves of hydrogen or helium pairs were obtained by molecular dynamics, and the energy of the most essential states was checked with DFT. Under assumptions of bubble formation due to trapping by similiar impurity atoms (self-trapping) or defects, KMCSs were carried out using parameters from implantation experiments. The results indicate that self-trapping plays no (or a very small) role in hydrogen bubble formation, whereas helium bubbles form due to strong self-trapping.}, + number = {1}, + urldate = {2019-11-05}, + journal = {Fusion Science and Technology}, + author = {Henriksson, K. O. E. and Nordlund, K. and Krasheninnikov, A. and Keinonen, J.}, + month = jul, + year = {2006}, + keywords = {Density Functional Theory, Bubble, Monte Carlo}, + pages = {43--57}, + file = {Henriksson et al. - 2006 - The Depths of Hydrogen and Helium Bubbles in Tungs.pdf:D\:\\Logiciels\\data_zotero\\storage\\5LPBPBIY\\Henriksson et al. - 2006 - The Depths of Hydrogen and Helium Bubbles in Tungs.pdf:application/pdf}, } -@article{anderl_deuteriumtritium_2004, - series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)}, - title = {Deuterium/tritium behavior in {Flibe} and {Flibe}-facing materials}, - volume = {329-333}, +@article{lee_hydrogen_2007, + series = {Plasma-{Surface} {Interactions}-17}, + title = {Hydrogen and helium trapping in tungsten under simultaneous irradiations}, + volume = {363-365}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311504003952}, - doi = {10.1016/j.jnucmat.2004.04.220}, - abstract = {Experimental studies to investigate the behavior of deuterium and tritium in the molten salt Flibe (2LiF·BeF2), have been conducted as part of the Japan–US joint research program (JUPITER-II). Measurements of deuterium transport were made in a cylindrically symmetric, dual permeation probe assembly containing 400 cc of Flibe. An exact analytical transport solution in cylindrical coordinates was fit to the measured permeation data, and this analysis derived deuterium diffusion and solubility coefficients of 8.0×10−10 m2/s and 3.1×10−4 mol/m3Pa at 600 °C, respectively, and 3.0×10−9 m2/s and 1.0×10−4 mol/m3Pa at 650 °C. The diffusion coefficients were about a factor of two less than previous results derived from capillary-reservoir diffusion measurements with tritium. Solubility results were significantly greater than previously measured for D2 but they were comparable to those for DF in Flibe. The results suggest that the dominant deuterium transport species in Flibe was D+F− for these experiments.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311507001754}, + doi = {10.1016/j.jnucmat.2007.01.111}, + abstract = {Hydrogen and helium trapping in polycrystalline tungsten under simultaneous He+–H+ and He+–D+ irradiation was measured by thermal desorption spectroscopy. At 300K: He retention and release are affected very little by the presence of H, closely following He+-only irradiations; He is trapped within ∼30nm of the surface. D retention is similar to D+-only levels but the presence of He enhances D trapping in the near surface, while limiting D diffusion into the bulk; D is trapped within ∼30–35nm of the surface possibly at interstitial sites surrounding He–vacancy defects. At 700K: He retention and release are again similar to He+-only cases; He is trapped within ∼30nm of the surface while no D is observed.}, language = {en}, - urldate = {2022-01-21}, + urldate = {2019-11-05}, journal = {Journal of Nuclear Materials}, - author = {Anderl, R. A and Fukada, S and Smolik, G. R and Pawelko, R. J and Schuetz, S. T and Sharpe, J. P and Merrill, B. J and Petti, D. A and Nishimura, H and Terai, T and Tanaka, S}, - month = aug, - year = {2004}, - pages = {1327--1331}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GYW23JA4\\S0022311504003952.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\57J3NPFW\\Anderl et al. - 2004 - Deuteriumtritium behavior in Flibe and Flibe-faci.pdf:application/pdf}, -} - -@incollection{kondo_606_2020, - address = {Oxford}, - title = {6.06 - {Liquid} {Breeder} {Materials}}, - isbn = {978-0-08-102866-7}, - url = {https://www.sciencedirect.com/science/article/pii/B9780128035818116194}, - abstract = {Self-cooled liquid blanket concepts are being studied for both magnetic confinement fusion reactors and inertial fusion reactors. The blanket structures can be simplified according to their multiple function such as a T breeder, a T transporter, a reactor coolant and a shielding material. There are several options for the blanket designs according to the selection of liquid breeder materials. Liquid Li reveals an excellent coolability according to its large heat transfer performance. Liquid Li alloys such as Pb-16Li and Sn-20Li reasonably contain the elements which function as a T breeder and a neutron multiplier. Liquid Pb­16Li is proposed as T breeder of ITER-TBM. Molten fluoride salts such as FLiBe and FLiNaBe have the advantage of chemical inertness and extremely low electrical conductivity which can practically eliminates MHD problems. The common issues of the liquid breeder materials are to clarify their T breeding performance, to control their T transfer behaviors, and to improve their material compatibility with structural and functional materials. This article reviews research findings on nuclear property, physical chemistry and material compatibility of liquid breeder materials.}, - language = {en}, - urldate = {2022-01-21}, - booktitle = {Comprehensive {Nuclear} {Materials} ({Second} {Edition})}, - publisher = {Elsevier}, - author = {Kondo, Masatoshi and Tanaka, Teruya and Fukada, Satoshi and Valentyn, Tsisar}, - editor = {Konings, Rudy J. M. and Stoller, Roger E.}, - month = jan, - year = {2020}, - doi = {10.1016/B978-0-12-803581-8.11619-4}, - keywords = {Tritium breeding, Corrosion, Molten salt, Blanket design, Liquid metal, Lithium, Material compatibility, Tritium solubility, Tritium transfer}, - pages = {176--202}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JTEEHCIK\\B9780128035818116194.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WB8HPG6G\\Kondo et al. - 2020 - 6.06 - Liquid Breeder Materials.pdf:application/pdf}, + author = {Lee, H. T. and Haasz, A. A. and Davis, J. W. and Macaulay-Newcombe, R. G. and Whyte, D. G. and Wright, G. M.}, + month = jun, + year = {2007}, + keywords = {Experiment}, + pages = {898--903}, + file = {Lee et al. - 2007 - Hydrogen and helium trapping in tungsten under sim.pdf:D\:\\Logiciels\\data_zotero\\storage\\6M9LWVWJ\\Lee et al. - 2007 - Hydrogen and helium trapping in tungsten under sim.pdf:application/pdf}, } -@article{lam_impact_2021, - title = {The impact of hydrogen valence on its bonding and transport in molten fluoride salts}, - volume = {9}, - issn = {2050-7488, 2050-7496}, - url = {http://xlink.rsc.org/?DOI=D0TA10576G}, - doi = {10.1039/D0TA10576G}, - abstract = {In molten fluoride salt systems, the chemistry and transport of hydrogen are coupled to its valence state, which controls the balance of tritium leakage and corrosion. - , - - Interest in molten salts has increased significantly over the last decade due to their potential application in various clean-energy technologies including hydrogen generation, solar heat storage, advanced fission nuclear power plants, and compact fusion energy systems. In nuclear fission and fusion power plants, high heat capacity molten salts allow operation at high temperature and atmospheric pressure, which could dramatically increase efficiency, reduce capital cost, and enable passive safety features. In many of these systems, the hydrogen isotope is of particular importance due to its ability to corrode structural materials as - 3 - H - + - in fluoride salts, and its potential to cause significant radioactive release as diffusive - 3 - H - 0 - , which are cited as key barriers to technological deployment. Yet, the chemistry and transport behavior of the hydrogen species remain poorly understood due to the difficulties in handling toxic salts and radioactive materials. Here, using - ab initio - molecular dynamics, we present a coupled examination of hydrogen speciation in the most common prototypical salts 66.6\% LiF–33.3\% BeF - 2 - (Flibe) and 46.5\% LiF–11.5\% NaF–42\% KF (Flinak). Using extensively validated calculations on the local structure and dynamics, we find significant difference between - 3 - H - 0 - and - 3 - H - + - transport behaviors that are usually overlooked. We find that - 3 - H - 0 - , which always exists as H - 2 - , diffuses 3–5 times faster than - 3 - H - + - , which can be ascribed to hydrogen bonding and complexation in solution. This work explains contradicting experimental results and provides useful species transport data for designing hydrogen capture and corrosion control systems for molten salts.}, +@article{ueda_simultaneous_2009, + series = {Fusion {Reactor} {Materials}}, + title = {Simultaneous irradiation effects of hydrogen and helium ions on tungsten}, + volume = {386-388}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311508009690}, + doi = {10.1016/j.jnucmat.2008.12.300}, + abstract = {Simultaneous irradiation effects of He on tungsten blistering with hydrogen and carbon mixed ion irradiation were investigated. It was found that only 0.1\% addition of He ions to 1keV H and C mixed ion beam (C: 0.8–1.0\%) reduced (473K) or completely suppressed (653K and 723K) blister formation. According to TEM observation, He bubbles with the size of 2nm or less were formed near the surface, which could be a diffusion barrier of hydrogen into the bulk due to the reduction of diffusion channel or excitation of stress field, leading to the reduction of diffusivity of hydrogen. The reduction rate of hydrogen inward flux by simultaneous He irradiation in our experimental conditions would be more than the factor of three.}, language = {en}, - number = {3}, - urldate = {2022-01-21}, - journal = {Journal of Materials Chemistry A}, - author = {Lam, Stephen T. and Li, Qing-Jie and Mailoa, Jonathan and Forsberg, Charles and Ballinger, Ronald and Li, Ju}, - year = {2021}, - pages = {1784--1794}, - file = {Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YN7LXZJM\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BV2BZKQY\\d0ta10576g.html:text/html;Supplementary Information PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\UYDU9QAG\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HE2H5H4D\\Lam et al. - 2021 - The impact of hydrogen valence on its bonding and .pdf:application/pdf}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Ueda, Y. and Fukumoto, M. and Yoshida, J. and Ohtsuka, Y. and Akiyoshi, R. and Iwakiri, H. and Yoshida, N.}, + month = apr, + year = {2009}, + keywords = {Experiment}, + pages = {725--728}, + file = {Ueda et al. - 2009 - Simultaneous irradiation effects of hydrogen and h.pdf:D\:\\Logiciels\\data_zotero\\storage\\8GZVVZND\\Ueda et al. - 2009 - Simultaneous irradiation effects of hydrogen and h.pdf:application/pdf}, } -@misc{noauthor_deuteriumtritium_nodate, - title = {Deuterium/tritium behavior in {Flibe} and {Flibe}-facing materials - {ScienceDirect}}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311504003952?via%3Dihub}, - urldate = {2022-01-21}, - file = {Deuterium/tritium behavior in Flibe and Flibe-facing materials - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4MDAIMLS\\S0022311504003952.html:text/html}, +@article{baldwin_effect_2011, + title = {Effect of {He} on {D} retention in {W} exposed to low-energy, high-fluence ({D}, {He}, {Ar}) mixture plasmas}, + volume = {51}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/0029-5515/51/10/103021/meta}, + doi = {10.1088/0029-5515/51/10/103021}, + abstract = {W targets are exposed at fixed temperature in the range ∼420–1100 K, to either pure D2, D2–δHe (0.1 {\textless} δ {\textless} 0.25), or D2–δHe–γAr (γ = 0.03) mixture plasma, or He pretreatment plasma followed by exposure to D2 plasma. A strong reduction in D retention is found for exposure temperature above 450 K and incident He-ion fluence exceeding ∼1024 m−2. Reduced D retention values lie well below that measured on D2 plasma-exposed reference targets, and the scatter in retention values reported in the literature. A small level of Ar admixture to D2–0.1He plasma, leading to an Ar ion density fraction of ∼3\%, is found to have minimal effect on the D inventory reduction caused by He. In targets with reduced inventory, nuclear-reaction analysis reveals shallow D trapping ({\textless}50 nm), in the same locale as nanometre-sized bubbles observed using transmission electron microscopy. It is suggested that near-surface bubbles grow and interconnect, forming pathways leading back to the plasma–material interaction surface, thereby interrupting transport to the bulk and reducing D retention.}, + language = {en}, + number = {10}, + urldate = {2019-11-04}, + journal = {Nuclear Fusion}, + author = {Baldwin, M. J. and Doerner, R. P. and Wampler, W. R. and Nishijima, D. and Lynch, T. and Miyamoto, M.}, + month = aug, + year = {2011}, + keywords = {Experiment}, + pages = {103021}, + annote = { +TDS are made on D and He +}, + file = {Baldwin et al. - 2011 - Effect of He on D retention in W exposed to low-en.pdf:D\:\\Logiciels\\data_zotero\\storage\\UCW4HSDR\\Baldwin et al. - 2011 - Effect of He on D retention in W exposed to low-en.pdf:application/pdf}, } -@article{fukada_hydrogen_2006, - title = {Hydrogen permeability through a mixed molten salt of {LiF}, {NaF} and {KF} ({Flinak}) as a heat-transfer fluid}, - volume = {358}, +@article{grigorev_mobility_2016, + title = {Mobility of hydrogen-helium clusters in tungsten studied by molecular dynamics}, + volume = {474}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311506004089}, - doi = {10.1016/j.jnucmat.2006.07.011}, - abstract = {Permeability, diffusivity and solubility of hydrogen in Flinak, a mixed molten salt of LiF (46.5\%), NaF (11.5\%) and KF (42\%), were determined using a vessel supported by a Ni plate. Diffusion-limiting permeation was confirmed by experimental data where hydrogen permeation rates were in reverse proportion to the thickness of Flinak. Diffusivities determined in the range of 500–750°C were correlated to an Arrhenius equation with the activation energy of 50kJ/mol. Since the dependence of hydrogen solubility in Flinak on pressure was almost linear, hydrogen was dissolved as H2 in Flinak. The H2 solubility in Flinak was correlated to a Henry law, and its solubility constant was discussed in terms of macroscopic surface tension and unspecified interaction energy between the molten salt and dissolved gaseous molecules.}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311516300952}, + doi = {10.1016/j.jnucmat.2016.03.022}, + abstract = {Tungsten is a primary candidate material for plasma facing components in fusion reactors. Interaction of plasma components with the material is unavoidable and will lead to degradation of the performance and the lifetime of the in-vessel components. In order to gain better understanding the mechanisms driving the material degradation at atomic level, atomistic simulations are employed. In this work we study migration, stability and self-trapping properties of pure helium and mixed helium-hydrogen clusters in tungsten by means of molecular dynamics simulations. We test two versions of an embedded atom model interatomic potential by comparing it with ab initio data regarding the binding properties of He clusters. By analysing the trajectories of the clusters during molecular dynamics simulations at finite temperatures we obtain the diffusion parameters. The results show that the diffusivity of mixed clusters is significantly lower, than that of pure helium clusters. The latter suggest that the formation of mixed clusters during mixed hydrogen helium plasma exposure will affect the helium diffusivity in the material.}, language = {en}, - number = {2}, - urldate = {2022-01-21}, + urldate = {2019-10-30}, journal = {Journal of Nuclear Materials}, - author = {Fukada, Satoshi and Morisaki, Akio}, - month = nov, - year = {2006}, - pages = {235--242}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PLDNDRA6\\S0022311506004089.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I28NCMQV\\Fukada et Morisaki - 2006 - Hydrogen permeability through a mixed molten salt .pdf:application/pdf}, + author = {Grigorev, Petr and Terentyev, Dmitry and Bonny, Giovanni and Zhurkin, Evgeny E. and van Oost, Guido and Noterdaeme, Jean-Marie}, + month = jun, + year = {2016}, + keywords = {Molecular Dynamics}, + pages = {143--149}, + file = {Grigorev et al. - 2016 - Mobility of hydrogen-helium clusters in tungsten s.pdf:D\:\\Logiciels\\data_zotero\\storage\\RGML8V9B\\Grigorev et al. - 2016 - Mobility of hydrogen-helium clusters in tungsten s.pdf:application/pdf}, } -@article{rota_measurements_1982, - title = {Measurements of surface and bulk properties for the interaction of hydrogen with inconel 600}, - volume = {111-112}, - issn = {00223115}, - url = {https://linkinghub.elsevier.com/retrieve/pii/0022311582902148}, - doi = {10.1016/0022-3115(82)90214-8}, +@article{grigorev_molecular_2018, + title = {Molecular dynamics simulation of hydrogen and helium trapping in tungsten}, + volume = {508}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311518301818}, + doi = {10.1016/j.jnucmat.2018.05.052}, + abstract = {Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material for plasma-facing components for future fusion reactors. Interaction of plasma components with the material leads to degradation of the performance and thus the lifetime of the in-vessel components. On top of that special attention is drawn to tritium retention in the reactors vessel from a safety point of view, since tritium is radioactive material. In order to gain better understanding of the mechanisms driving accumulation of plasma components in the material and subsequent degradation of the material, atomistic simulations are employed. The focus of this work is on so-called self trapping of H and He atoms or, in other words, Frenkel pair formation in bulk tungsten in the presence of H and He atoms. Two versions of a model embedded atom interatomic potential and a bond order potential were tested by comparing it with ab initio data regarding the binding properties of pure He and He-H-Vacancy clusters and energetics of Frenkel pair formation. As a result of Molecular Dynamics simulations at finite temperature, the values of critical H concentration needed for the generation of a Frenkel pair in the presence of He clusters were obtained. The results show that the critical H concentration decreases with the size of He cluster present in the simulation cell and thus, Frenkel pair formation by H is facilitated in the presence of He clusters in the material.}, language = {en}, - urldate = {2022-01-21}, + urldate = {2019-10-30}, journal = {Journal of Nuclear Materials}, - author = {Rota, E. and Waelbroeck, F. and Wienhold, P. and Winter, J.}, - month = nov, - year = {1982}, - pages = {233--239}, - file = {Rota et al. - 1982 - Measurements of surface and bulk properties for th.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\U62D5GXG\\Rota et al. - 1982 - Measurements of surface and bulk properties for th.pdf:application/pdf}, + author = {Grigorev, Petr and Zinovev, Aleksandr and Terentyev, Dmitry and Bonny, Giovanni and Zhurkin, Evgeny E. and Van Oost, Guido and Noterdaeme, Jean-Marie}, + month = sep, + year = {2018}, + keywords = {Molecular Dynamics}, + pages = {451--458}, + file = {Grigorev et al. - 2018 - Molecular dynamics simulation of hydrogen and heli.pdf:D\:\\Logiciels\\data_zotero\\storage\\S3XRPWTA\\Grigorev et al. - 2018 - Molecular dynamics simulation of hydrogen and heli.pdf:application/pdf}, } -@article{bai_efficient_2010, - title = {Efficient {Annealing} of {Radiation} {Damage} {Near} {Grain} {Boundaries} via {Interstitial} {Emission}}, - volume = {327}, - issn = {0036-8075, 1095-9203}, - url = {https://www.science.org/doi/10.1126/science.1183723}, - doi = {10.1126/science.1183723}, +@article{wan_hydrogen_2018, + title = {Hydrogen trapping in helium-implanted {W} and {W}-{Ta} alloy: {First}-principles approach}, + volume = {508}, + issn = {0022-3115}, + shorttitle = {Hydrogen trapping in helium-implanted {W} and {W}-{Ta} alloy}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311518300060}, + doi = {10.1016/j.jnucmat.2018.05.050}, + abstract = {We reveal the interaction of H with He in pure W and W-Ta alloy based on first-principles calculations. We show a strong attraction between H and He in both systems that drives H segregation towards He. The substitutional He and tetrahedral interstitial H defects in W-Ta alloy are more energetically favorable than pure W due to the decreased electronic density of the replaced Ta atom. Moreover, 1 He-Vac complex in both systems can trap as many as 12 H atoms. Based on the calculated formation energy of Hn-He-Vac complexes, the H3-He-Vac has the lowest formation energy in both systems. We believe that such understanding is generally applicable for H bubble formation in metals and metal alloys.}, language = {en}, - number = {5973}, - urldate = {2022-01-05}, - journal = {Science}, - author = {Bai, Xian-Ming and Voter, Arthur F. and Hoagland, Richard G. and Nastasi, Michael and Uberuaga, Blas P.}, - month = mar, - year = {2010}, - pages = {1631--1634}, - file = {Bai et al. - 2010 - Efficient Annealing of Radiation Damage Near Grain.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BR6YTNKT\\Bai et al. - 2010 - Efficient Annealing of Radiation Damage Near Grain.pdf:application/pdf}, + urldate = {2019-11-07}, + journal = {Journal of Nuclear Materials}, + author = {Wan, ChuBin and Yu, SuYe and Ju, Xin and Wang, WenWen}, + month = sep, + year = {2018}, + keywords = {Density Functional Theory}, + pages = {249--256}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CY6G5U3P\\S0022311518300060.html:text/html;Wan et al. - 2018 - Hydrogen trapping in helium-implanted W and W-Ta a.pdf:D\:\\Logiciels\\data_zotero\\storage\\NQQA4KE3\\Wan et al. - 2018 - Hydrogen trapping in helium-implanted W and W-Ta a.pdf:application/pdf}, } -@article{zhou_simultaneous_2019, - title = {A simultaneous corrosion/irradiation facility for testing molten salt-facing materials}, - volume = {440}, - issn = {0168-583X}, - url = {https://www.sciencedirect.com/science/article/pii/S0168583X18306700}, - doi = {10.1016/j.nimb.2018.11.024}, - abstract = {Aside from the historical Molten Salt Reactor Experiment, a few in-reactor loops, and one electron irradiation/corrosion facility, dedicated facilities to test the combined effects of molten salt corrosion and irradiation on materials do not currently exist. A major gap therefore exists in rapid, reactor-relevant materials testing capabilities which, if remedied, would greatly hasten molten salt reactor development. We present a new accelerator-based facility for rapid, simultaneous testing of molten salt-facing materials utilizing a proton beam as the radiation source. Introducing proton irradiation to a molten salt corrosion system poses specific engineering concerns in sample and corrosion cell design, operational stability, integration with the accelerator beamline, and radiation safety. This paper describes how these requirements were fulfilled with confirmatory tests and results.}, +@article{yang_effect_2018, + title = {Effect of interatomic potential on the energetics of hydrogen and helium-vacancy complexes in bulk, or near surfaces of tungsten}, + volume = {512}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311518310766}, + doi = {10.1016/j.jnucmat.2018.10.032}, + abstract = {Hydrogen (H) trapping by helium-vacancy (HeV) complexes in bulk and the near surface region of tungsten (W) have been investigated by molecular statics calculations that evaluate two different WH interatomic potentials, which use the same WHe, HeHe and HeH potentials. One of the WH potentials is a bond-order potential (BOP) developed by Juslin et al., while the other is an embedding atom method (EAM) potential developed by Wang et al.. Both potentials overestimate the H binding energies to He clusters in bulk W, as compared to DFT calculations, but properly predict the functional form of the H binding energies to He clusters with increasing number of He and H. The BOP simulations reveal that H binding energies to HexV complexes generally increase with increasing number of He. However, the EAM results indicate that the H binding energy as a function of number of He depends on the number of H, and the H binding energies change slightly at high He content. Compared with available DFT data, both BOP and EAM underestimate the H binding energies to HexV2Hm complexes. The BOP reproduces the He formation energy below a W surface, while the EAM potential better reproduces the H formation energy and the interactions between H and HeV complexes. Based on these comparisons, we determine that the EAM potential is more accurate than BOP for large-scale molecular dynamics simulations of WHeH interactions. The EAM potential predicts that the difference in the average binding energies of H to stable HeV complexes near the W surface is less than 0.2 eV and the difference decreases with increasing He content. Thus, the EAM potential indicates that the effect of surfaces on H binding energies to large HeV complexes below the W surfaces can be ignored.}, language = {en}, - urldate = {2022-01-05}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Zhou, Weiyue and Woller, Kevin B. and Zheng, Guiqiu (Tony) and Stahle, Peter W. and Short, Michael P.}, - month = feb, - year = {2019}, - keywords = {Corrosion, Molten salt, Radiation}, - pages = {54--59}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZVPNSAJQ\\S0168583X18306700.html:text/html}, + urldate = {2019-11-07}, + journal = {Journal of Nuclear Materials}, + author = {Yang, L. and Bergstrom, Z. J. and Wirth, B. D.}, + month = dec, + year = {2018}, + keywords = {Density Functional Theory}, + pages = {357--370}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\F9A8952E\\Yang et al. - 2018 - Effect of interatomic potential on the energetics .pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\22YCX396\\S0022311518310766.html:text/html}, } -@article{forsberg_fusion_2020, - title = {Fusion {Blankets} and {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} with {Flibe} {Salt} {Coolant}: {Common} {Challenges}, {Tritium} {Control}, and {Opportunities} for {Synergistic} {Development} {Strategies} {Between} {Fission}, {Fusion}, and {Solar} {Salt} {Technologies}}, - volume = {206}, - issn = {0029-5450}, - shorttitle = {Fusion {Blankets} and {Fluoride}-{Salt}-{Cooled} {High}-{Temperature} {Reactors} with {Flibe} {Salt} {Coolant}}, - url = {https://doi.org/10.1080/00295450.2019.1691400}, - doi = {10.1080/00295450.2019.1691400}, - abstract = {Recent developments in high-magnetic-field fusion systems have created large incentives to develop flibe (Li2BeF4) salt fusion blankets that have four functions: (1) convert the high energy of fusion neutrons into heat for the power system, (2) convert lithium into tritium—the fusion fuel, (3) shield the magnets against radiation, and (4) cool the first wall that separates the plasma from the salt blanket. Flibe is the same coolant proposed for fluoride-salt-cooled high-temperature reactors that use clean flibe coolant and graphite-matrix coated-particle fuel. Flibe is also the coolant proposed for some molten salt reactors (MSRs) where the fuel is dissolved in the coolant. The multiple applications for flibe as a coolant create large incentives for cooperative fusion-fission programs for development of the underlying science, design tools, technology (pumps, instrumentation, salt purification, materials, tritium removal, etc.), and supply chains. Other high-temperature molten salts are being developed for alternative MSR systems and for advanced Gen-III concentrated solar power (CSP) systems. The overlapping characteristics of flibe salt with these other salt systems create significant incentives for cooperative fusion-fission-solar programs in multiple areas.We describe the fission and fusion flibe-cooled systems, what has created this synergism, what is different and the same between fission and fusion in terms of using flibe, and the common challenges. We review (1) the characteristics of flibe salts, (2) the status of the technology, (3) the options for tritium capture and control in the salt, heat exchangers, and secondary heat transfer loops, and (4) the coupling to power cycles with heat storage. The technology overlap between flibe systems and other high-temperature MSR and CSP salt systems is described. This defines where there are opportunities for cooperative programs across fission, fusion, and CSP salt programs.}, - number = {11}, - urldate = {2022-01-04}, - journal = {Nuclear Technology}, - author = {Forsberg, Charles and Zheng, Guiqiu (Tony) and Ballinger, Ronald G. and Lam, Stephen T.}, - month = nov, - year = {2020}, - note = {Publisher: Taylor \& Francis -\_eprint: https://doi.org/10.1080/00295450.2019.1691400}, - keywords = {flibe salt, fluoride-salt-cooled high-temperature reactor, fusion, molten salt reactor, Salt-cooled reactors}, - pages = {1778--1801}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S6FCKS69\\00295450.2019.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XE4HZVFD\\Forsberg et al. - 2020 - Fusion Blankets and Fluoride-Salt-Cooled High-Temp.pdf:application/pdf}, +@article{rieth_behavior_2019, + title = {Behavior of tungsten under irradiation and plasma interaction}, + volume = {519}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S002231151930025X}, + doi = {10.1016/j.jnucmat.2019.03.035}, + language = {en}, + urldate = {2019-11-07}, + journal = {Journal of Nuclear Materials}, + author = {Rieth, Michael and Doerner, Russell and Hasegawa, Akira and Ueda, Yoshio and Wirtz, Marius}, + month = jun, + year = {2019}, + pages = {334--368}, + file = {Rieth et al. - 2019 - Behavior of tungsten under irradiation and plasma .pdf:D\:\\Logiciels\\data_zotero\\storage\\KRUH66F5\\Rieth et al. - 2019 - Behavior of tungsten under irradiation and plasma .pdf:application/pdf}, } -@article{zeng_behavior_2019, - title = {Behavior characteristics of hydrogen and its isotope in molten salt of {LiF}-{NaF}-{KF} ({FLiNaK})}, - volume = {51}, - issn = {1738-5733}, - url = {https://www.sciencedirect.com/science/article/pii/S1738573318301967}, - doi = {10.1016/j.net.2018.10.008}, - abstract = {Experimental studies to investigate the behaviors of hydrogen in molten FLiNaK (LiF-NaF-KF) have been conducted at 500–700 °C. On the basis of previous studies, the diffusivity and solubility of hydrogen in FLiNaK have been revised, and the expressions can be correlated to the following Arrhenius equations: DH2 = 1.62 × 10−5exp (−48.20 × 103/Rg·T) [m2/s] and SH2 = 1.03 × 10−4exp (−14.96 × 103/Rg·T) [mol-H2/m3/Pa], respectively. The behavior characteristics of deuterium in FLiNaK were studied and compared with the hydrogen behaviors in FLiNaK. The results showed the behaviors of deuterium were consistence with the behaviors of hydrogen in FLiNaK. The difference between hydrogen and deuterium has not been observed upon the experimental research of the behavior characteristics of hydrogen and deuterium in FLiNaK, which suggested the results obtained here might apply equally to the behavior characteristics of tritium in FLiNaK.}, +@article{panizo-laiz_experimental_2019, + title = {Experimental and computational studies of the influence of grain boundaries and temperature on the radiation-induced damage and hydrogen behavior in tungsten}, + volume = {59}, + issn = {0029-5515}, + url = {https://iopscience.iop.org/article/10.1088/1741-4326/ab26e9}, + doi = {10.1088/1741-4326/ab26e9}, + abstract = {We study the influence of grain boundaries (GBs) on radiation-induced vacancies, as well as on the hydrogen (H) behavior in tungsten (W) samples with different grain sizes in the temperature range from 300 K to 573 K, both experimentally and by computer simulations. For this purpose, coarse-grained and nanostructured W samples were sequentially irradiated with carbon (C) and H ions at energies of 665 keV and 170 keV, respectively. A first set of the implanted samples was annealed at 473 K and a second set at 573 K. Object kinetic Monte Carlo simulations were performed to account for experimental outcomes. Results show that the number of vacancies for nanostructured W is always larger than for monocrystalline W samples in the whole studied temperature range and that the number of vacancies is only reduced in samples with a large density of grain boundaries and at temperatures high enough to activate the vacancy motion (around 573 K). Results also indicate that the migration of H along vacancy free grain boundaries is more effective than along the bulk, and that the retained H is trapped in vacancies located within the grains. These results are used to explain the experimental outcomes.}, language = {en}, - number = {2}, - urldate = {2022-01-04}, - journal = {Nuclear Engineering and Technology}, - author = {Zeng, Youshi and Liu, Wenguan and Liu, Wei and Qian, Yuan and Qian, Nan and Wu, Xiaoling and Huang, Yu and Wu, Shengwei and Wang, Guanghua}, - month = apr, + number = {8}, + urldate = {2019-11-05}, + journal = {Nuclear Fusion}, + author = {Panizo-Laiz, M. and Díaz-Rodríguez, P. and Rivera, A. and Valles, G. and Martín-Bragado, I. and Perlado, J. M. and Munnik, F. and González-Arrabal, R.}, + month = jul, year = {2019}, - keywords = {Deuterium, Diffusion, Hydrogen, Molten FLiNaK, Permeation}, - pages = {490--494}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9VVKKZZR\\S1738573318301967.html:text/html}, + keywords = {Monte Carlo}, + pages = {086055}, + file = {Panizo-Laiz et al. - 2019 - Experimental and computational studies of the infl.pdf:D\:\\Logiciels\\data_zotero\\storage\\SYIEQ89A\\Panizo-Laiz et al. - 2019 - Experimental and computational studies of the infl.pdf:application/pdf}, } -@article{song_tritium_2010, - series = {Proceedings of the {Ninth} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, - title = {Tritium analysis of fusion-based hydrogen production reactor {FDS}-{III}}, - volume = {85}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379610000098}, - doi = {10.1016/j.fusengdes.2010.01.008}, - abstract = {A dynamic subsystem model of tritium fuel cycle for the FDS-III was developed, and the required minimum tritium supply for reactor startup and the doubling time for tritium breeding were calculated by using the Tritium Analysis Software (TAS). Some factors which would affect the tritium supply and doubling time were considered, such as the tritium fractional burnup in the plasma, tritium breeding ratio (TBR), the residence time of tritium in all subsystems, and tritium decay, etc. The results showed that the minimum tritium supply for startup was sensitive with the tritium fractional burnup in the plasma, but the effect of the TBR could be neglected. The double time for tritium breeding strongly depended on the TBR and the tritium fractional burnup. Based on the model, the analysis results predicted that the required initial minimum tritium supply was ∼9.9kg for startup. After one year's operation, the total tritium inventory in fuel cycle system was ∼33kg. And the total tritium release into environment was ∼4mg, which was much lower than the allow level, i.e. 1g-T/year. The tritium in fuel storage system would be doubled and could be extracted to supply for the other fusion power reactor's startup after ∼886days operation.}, +@article{becquart_migration_2006, + title = {Migration {Energy} of {He} in {W} {Revisited} by {Ab} {Initio} {Calculations}}, + volume = {97}, + url = {https://link.aps.org/doi/10.1103/PhysRevLett.97.196402}, + doi = {10.1103/PhysRevLett.97.196402}, + abstract = {We use state of the art ab initio calculations to obtain the diffusion properties of He in tungsten. The calculated migration energy of He is very low, around 0.06 eV. This value is much lower than the experimental field-ion microscopy results which lead to a migration energy of the order of 0.24—0.32 eV. The reason for this discrepancy is the high propensity for He to form He-He clusters characterized by a very large binding energy of the order of 1 eV. Such a large binding energy indicates that He atoms can be trapped by other He atoms and can explain the formation of He blisters close to the surface of He implanted tungsten.}, + number = {19}, + urldate = {2019-10-30}, + journal = {Physical Review Letters}, + author = {Becquart, Charlotte S. and Domain, Christophe}, + month = nov, + year = {2006}, + keywords = {Density Functional Theory}, + pages = {196402}, + file = {Becquart et Domain - 2006 - Migration Energy of He in W Revisited by Ab Initio.pdf:D\:\\Logiciels\\data_zotero\\storage\\IYHTPYVG\\Becquart et Domain - 2006 - Migration Energy of He in W Revisited by Ab Initio.pdf:application/pdf}, +} + +@article{takayama_first_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {First principles investigation of cluster consisting of hydrogen–helium atoms interstitially-trapped in tungsten}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S002231151400782X}, + doi = {10.1016/j.jnucmat.2014.11.001}, + abstract = {We evaluate the binding energies of mixed helium and hydrogen clusters consisted of interstitially trapped atoms in bcc tungsten by first-principles calculations based on density functional theories. It is shown that helium-rich interstitially-trapped clusters have the positive binding energies and the low electron-density region expand as the number of helium in the cluster increase. Thus, the helium-rich interstitially trapped clusters can act as a trapping site for hydrogen, and interstitially trapped helium interrupts or disturbs the hydrogen diffusion in tungsten.}, language = {en}, - number = {7}, - urldate = {2021-12-27}, - journal = {Fusion Engineering and Design}, - author = {Song, Yong and Huang, Qunying and Ni, Muyi}, - month = dec, - year = {2010}, - keywords = {Tritium management, Fusion reactor, High temperature blanket}, - pages = {1044--1047}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Takayama, A. and Ito, A. M. and Oda, Y. and Nakamura, H.}, + month = aug, + year = {2015}, + keywords = {Density Functional Theory}, + pages = {355--358}, + annote = { +DFT calculations. +Future work: MD of clusters He/H. +}, + file = {Takayama et al. - 2015 - First principles investigation of cluster consisti.pdf:D\:\\Logiciels\\data_zotero\\storage\\XDGGDE55\\Takayama et al. - 2015 - First principles investigation of cluster consisti.pdf:application/pdf}, } -@article{deng_tritium_2011, - title = {Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention}, - volume = {51}, - issn = {0029-5515, 1741-4326}, - url = {https://iopscience.iop.org/article/10.1088/0029-5515/51/7/073041}, - doi = {10.1088/0029-5515/51/7/073041}, - abstract = {New simulation results are predicted in a fusion reactor operation process. They are somewhat similar to, but quite different from, the xenon poisoning effects resulting from fission-produced iodine during the restart-up process of a fission reactor. We obtained completely new results of tritium well depth and tritium well time in magnetic confinement fusion energy research area. This study is carried out to investigate the following: what will be the least amount of tritium storage required to start up a fusion reactor and how long the fusion reactor needs to be operated for achieving the tritium break-even during the initial start-up phase due to the finite tritium-breeding time, which is dependent on the tritium breeder, specific structure of the breeding zone, layout of the coolant flow pipes, tritium recovery scheme and applied extraction process, the tritium retention of plasma facing component (PFC) and other reactor components, unrecoverable tritium fraction in the breeder, leakage to the inertial gas container and the natural radioactive decay time constant. We describe these new issues and answer these problems by setting up and solving a set of equations, which are described by a dynamic subsystem model of tritium inventory evolution in a fusion experimental breeder (FEB). Reasonable results are obtained using our simulation model. It is found that the tritium well depth is about 0.319 kg and the tritium well time is approximately 235 full power operation days for the reference case of the designed FEB configuration, and it is also found that after one-year operation the tritium storage reaches 0.767 kg, which is more than the least amount of tritium storage required to start up another FEB-like fusion reactor. The results show that the tritium retention in the PFC is equivalent to 11.9\% of tritium well depth that is fairly consistent with the result of 10–20\% deduced from the integrated particle balance of European tokamaks. Based on our experimental and theoretical studies, some new mechanisms are proposed for reducing the tritium retention in PFC and structure materials of tritium-breeding blanket. In this paper, a qualitative analysis of the ‘sponge effect’ is carried out. The ‘sponge effect’ may help us to reduce tritium retention by ∼20\% in the PFC.}, +@article{hodille_hydrogen_2018, + title = {Hydrogen supersaturated layers in {H}/{D} plasma-loaded tungsten: {A} global model based on thermodynamics, kinetics and density functional theory data}, + volume = {2}, + shorttitle = {Hydrogen supersaturated layers in {H}/{D} plasma-loaded tungsten}, + url = {https://link.aps.org/doi/10.1103/PhysRevMaterials.2.093802}, + doi = {10.1103/PhysRevMaterials.2.093802}, + abstract = {In this paper, we combine density functional theory data with a thermodynamic and a kinetic model to determine the total concentration of hydrogen implanted in the subsurface of tungsten exposed to a hydrogen flux. The subsurface hydrogen concentration is calculated given a flux of hydrogen, a temperature of implantation, and the energy of the incoming hydrogen ions as independent variables. This global model is built step by step; an equilibrium between atomic hydrogen within bulk tungsten and a molecular hydrogen gas phase is first considered, and the calculated solubility is compared with experimental results. Subsequently, a kinetic model is used to determine the chemical potential for hydrogen in the subsurface of tungsten. Combining both these models, two regimes are established in which hydrogen is preferentially trapped either at interstitial sites or in vacancies. We deduce from our model that the existence of these two regimes is driven by the temperature of the implanted tungsten sample; above a threshold or transition temperature is the interstitial regime, and below is the vacancy regime in which supersaturated layers form within tenths of an angstrom below the surface. A simple analytical expression is derived for the coexistence of the two regimes depending on the implantation temperature, the incident energy, and the flux of the hydrogen ions which we use to plot the corresponding phase diagram.}, + number = {9}, + urldate = {2019-10-07}, + journal = {Physical Review Materials}, + author = {Hodille, E. A. and Fernandez, N. and Piazza, Z. A. and Ajmalghan, M. and Ferro, Y.}, + month = sep, + year = {2018}, + keywords = {Density Functional Theory}, + pages = {093802}, +} + +@article{kato_super-saturated_2015, + title = {Super-saturated hydrogen effects on radiation damages in tungsten under the high-flux divertor plasma irradiation}, + volume = {55}, + issn = {0029-5515}, + doi = {10.1088/0029-5515/55/8/083019}, + abstract = {Tungsten is a prime candidate as the divertor material of the ITER and DEMO reactors, which would be exposed to unprecedentedly high-flux plasmas as well as neutrons. For a better characterization of radiation damages in the tungsten under the divertor condition, we examine influences of super-saturated hydrogen on vacancies in the tungsten. The present calculations based on density functional theory (DFT) reveal unusual phenomena predicted at a super-saturated hydrogen concentration: (1) strongly enhanced vacancy concentration with the super-saturated hydrogen concentration is predicted by a thermodynamics model assuming multiple-hydrogen trapping, i.e. hydrogen clusters formation, in the vacancies; and (2) DFT molecular dynamics revealed that hydrogen clusters can prevent a vacancy from recombining with the neighboring crowdion-type self-interstitial-atom. This suggests that neutron damage effects will be increased in the presence of the hydrogen clusters.}, language = {en}, - number = {7}, - urldate = {2021-12-27}, + number = {8}, + urldate = {2019-10-07}, journal = {Nuclear Fusion}, - author = {Deng, B.Q. and Li, Z.X. and Li, C.Y. and Feng, K.M.}, + author = {Kato, D. and Iwakiri, H. and Watanabe, Y. and Morishita, K. and Muroga, T.}, month = jul, - year = {2011}, - pages = {073041}, - file = {Deng et al. - 2011 - Tritium well depth, tritium well time and sponge m.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NFGSJCQ3\\Deng et al. - 2011 - Tritium well depth, tritium well time and sponge m.pdf:application/pdf}, + year = {2015}, + keywords = {Density Functional Theory}, + pages = {083019}, + file = {Kato et al. - 2015 - Super-saturated hydrogen effects on radiation dama.pdf:D\:\\Logiciels\\data_zotero\\storage\\UZTTL3RP\\Kato et al. - 2015 - Super-saturated hydrogen effects on radiation dama.pdf:application/pdf}, } -@article{liu_analysis_2020, - title = {Analysis of the whole process tritium transport based on fuel cycle modeling for {CFETR}}, - volume = {161}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379620306086}, - doi = {10.1016/j.fusengdes.2020.112060}, - abstract = {Tritium self-sustain is crucial for the successful operation of China Fusion Engineering Test Reactor (CFETR). In this work, tritium fuel cycle model is developed based on the practical tritium plant. The retention values caused by different purification technology which can’t be extracted during the fuel cycle is considered in several sub-systems like Isotope Separation System-Inner cycle(ISS-I). The typical inventory in each sub-system is calculated which resulting that the minimum initial startup inventory (Im) is about 3131 g and tritium breeding ratio that required to satisfy tritium self-sustain (TBRreq) is about 1.13 under typical parameters. The sensitivity relation of Im and TBRreq are analyzed. We found that the fractional burnup is a key factor to affect both.}, +@article{begrambekov_hydrogen_2014, + title = {Hydrogen transport through oxide metal surface under atom and ion irradiation}, + volume = {567}, + issn = {1742-6596}, + doi = {10.1088/1742-6596/567/1/012003}, + abstract = {Both the latest and earlier achieved results on gas exchange processes on metal surfaces (including stainless steel, titanium, zirconium, tungsten with deposited aluminum oxide coating) under hydrogen atom or plasma irradiation with occasional oxygen impurity are presented in the paper. Mechanisms and regularities of these processes are discussed. It is demonstrated that surface oxide layer properties as a diffusion barrier strongly depend on external influence on the surface. In particular, it is revealed that low energy hydrogen ion irradiation could slow down hydrogen desorption from metals. Hydrogen atom or ion irradiation combined with simultaneous oxygen admixture accelerates hydrogen desorption from metals.}, language = {en}, - urldate = {2021-12-27}, - journal = {Fusion Engineering and Design}, - author = {Liu, Linzi and Tong, Ruihai and Cai, Jinguang and Yao, Yong and Song, Jiangfeng and Chen, Chang’an and Luo, Deli and Yao, Weizhi}, - month = dec, - year = {2020}, - keywords = {Mean residence time, Tritium fuel cycle modeling, Tritium self-sustain}, - pages = {112060}, + journal = {Journal of Physics: Conference Series}, + author = {Begrambekov, L. and Dvoychenkova, O. and Evsin, A. and Kaplevsky, A. and Sadovskiy, Ya and Schitov, N. and Vergasov, S. and Yurkov, D.}, + month = nov, + year = {2014}, + pages = {012003}, + file = {Begrambekov et al. - 2014 - Hydrogen transport through oxide metal surface und.pdf:D\:\\Logiciels\\data_zotero\\storage\\BP4893KY\\Begrambekov et al. - 2014 - Hydrogen transport through oxide metal surface und.pdf:application/pdf}, } -@misc{day_tritium_2016, - title = {Tritium fuel cycle and self-sufficiency - {R}\&{D} for {DEMO} and required extrapolations beyond {ITER}}, +@article{wirth_challenges_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Challenges and opportunities of modeling plasma–surface interactions in tungsten using high-performance computing}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514008757}, + doi = {10.1016/j.jnucmat.2014.11.072}, + abstract = {The performance of plasma facing components (PFCs) is critical for ITER and future magnetic fusion reactors. The ITER divertor will be tungsten, which is the primary candidate material for future reactors. Recent experiments involving tungsten exposure to low-energy helium plasmas reveal significant surface modification, including the growth of nanometer-scale tendrils of “fuzz” and formation of nanometer-sized bubbles in the near-surface region. The large span of spatial and temporal scales governing plasma surface interactions are among the challenges to modeling divertor performance. Fortunately, recent innovations in computational modeling, increasingly powerful high-performance computers, and improved experimental characterization tools provide a path toward self-consistent, experimentally validated models of PFC and divertor performance. Recent advances in understanding tungsten–helium interactions are reviewed, including such processes as helium clustering, which serve as nuclei for gas bubbles; and trap mutation, dislocation loop punching and bubble bursting; which together initiate surface morphological modification.}, language = {en}, - author = {Day, Christian}, - month = nov, - year = {2016}, - file = {Day - Tritium fuel cycle and self-sufficiency - R&D for .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FMLU5FXJ\\Day - Tritium fuel cycle and self-sufficiency - R&D for .pdf:application/pdf}, + urldate = {2019-10-30}, + journal = {Journal of Nuclear Materials}, + author = {Wirth, Brian D. and Hammond, K. D. and Krasheninnikov, S. I. and Maroudas, D.}, + month = aug, + year = {2015}, + pages = {30--38}, + file = {Wirth et al. - 2015 - Challenges and opportunities of modeling plasma–su.pdf:D\:\\Logiciels\\data_zotero\\storage\\BESUFI9U\\Wirth et al. - 2015 - Challenges and opportunities of modeling plasma–su.pdf:application/pdf}, } -@article{abdou_blanketfirst_2015, - title = {Blanket/first wall challenges and required {R}\&{D} on the pathway to {DEMO}}, - volume = {100}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379615302465}, - doi = {10.1016/j.fusengdes.2015.07.021}, - abstract = {The breeding blanket with integrated first wall (FW) is the key nuclear component for power extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER device will address plasma burn physics and plasma support technology, but it does not have a breeding blanket. Current activities to develop “roadmaps” for realizing fusion power recognize the blanket/FW as one of the principal remaining challenges. Therefore, a central element of the current planning activities is focused on the question: what are the research and major facilities required to develop the blanket/FW to a level which enables the design, construction and successful operation of a fusion DEMO? The principal challenges in the development of the blanket/FW are: (1) the Fusion Nuclear Environment – a multiple-field environment (neutrons, heat/particle fluxes, magnetic field, etc.) with high magnitudes and steep gradients and transients; (2) Nuclear Heating in a large volume with sharp gradients – the nuclear heating drives most blanket phenomena, but accurate simulation of this nuclear heating can be done only in a DT-plasma based facility; and (3) Complex Configuration with blanket/first wall/divertor inside the vacuum vessel – the consequence is low fault tolerance and long repair/replacement time. These blanket/FW development challenges result in critical consequences: (a) non-fusion facilities (laboratory experiments) need to be substantial to simulate multiple fields/multiple effects and must be accompanied by extensive modeling; (b) results from non-fusion facilities will be limited and will not fully resolve key technical issues. A DT-plasma based fusion nuclear science facility (FNSF) is required to perform “multiple effects” and “integrated” experiments in the fusion nuclear environment; and (c) the Reliability/Availability/Maintainability/Inspectability (RAMI) of fusion nuclear components is a major challenge and is one of the primary reasons why the blanket/FW will pace fusion development toward a DEMO. This paper summarizes the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identifies the key R\&D needs in non-fusion and fusion facilities on the path to DEMO.}, +@article{pezzoli_thermal_2015, + series = {{PLASMA}-{SURFACE} {INTERACTIONS} 21}, + title = {Thermal annealing and exposure to divertor-like deuterium plasma of tailored tungsten oxide coatings}, + volume = {463}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311514008265}, + doi = {10.1016/j.jnucmat.2014.11.035}, + abstract = {In this work we produced tungsten (W) and W oxide (WOx) films by pulsed laser deposition (PLD) with the aim of the addressing modifications of structure and morphology that occur after annealing treatments and high-flux deuterium plasma. Thanks to the high flexibility of PLD we produced nanostructured W containing non-bounded oxygen, different types of WOx and multilayered films. W coatings are dense, non-porous and exhibit a nanocrystalline structure, resembling the coatings used as first wall in tokamaks. The oxide films are nearly stoichiometric amorphous WOx (x=3) with different morphology from compact to porous. Depending on annealing temperature, nucleation of different crystalline phases (e.g. WO3, W18O49) occurs. Exposure of films to high-flux (∼1024m−2s−1) deuterium plasmas in Magnum-PSI at different surface temperatures (Tmax=580K) determines material modifications at the nanoscale (e.g. nanometric defects) but no delamination. In addition preliminary deuterium retention results are reported.}, language = {en}, - urldate = {2021-12-27}, - journal = {Fusion Engineering and Design}, - author = {Abdou, Mohamed and Morley, Neil B. and Smolentsev, Sergey and Ying, Alice and Malang, Siegfried and Rowcliffe, Arthur and Ulrickson, Mike}, - month = nov, + urldate = {2019-10-25}, + journal = {Journal of Nuclear Materials}, + author = {Pezzoli, A. and Dellasega, D. and Russo, V. and Gallo, A. and Zeijlmans van Emmichoven, P. A. and Passoni, M.}, + month = aug, year = {2015}, - keywords = {First wall, MHD, Materials, Liquid metals, Fusion nuclear science facility, Mass transfer, Blanket, Ceramic breeders, DCLL, Fusion nuclear technology, Fusion technology, Heat transfer, Tritium self-sufficiency}, - pages = {2--43}, + pages = {1041--1044}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\46RUDJNV\\Pezzoli et al. - 2015 - Thermal annealing and exposure to divertor-like de.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4TUHYL4L\\S0022311514008265.html:text/html}, } -@article{busigin_dynamic_1992, - title = {Dynamic {Simulation} of the {ITER} {Fuel} {Cycle}}, - volume = {21}, - issn = {0748-1896}, - url = {https://www.tandfonline.com/doi/full/10.13182/FST92-A29867}, - doi = {10.13182/FST92-A29867}, - abstract = {А dynamic simulation has been developed for the ITER fuel cycle including vacuum pumpi11g, fuel processing, fueling, pellet injection, tritium breeding Ьlanket detritiation, fuel purification and isotope separation. The dynamic simulatio11 model is used for calculating the unsteady-state flow of materials throug{\textbackslash}1 tl1e various fuel processing systems. Since many of the systems have substantial hold-up times, and the ITER l"eactor burn and dwell cycle is periodic, а steady state model cannot provide а complete picture of system behavior. The dynamic model allows assessment of flowrates and minimum and maximum inveнtories under а wide range of dynamic conditions. This info1·mation is necessary for proper specification of system design requirements.}, +@article{longhurst_soret_1985, + title = {The soret effect and its implications for fusion reactors}, + volume = {131}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/0022311585904258}, + doi = {10.1016/0022-3115(85)90425-8}, + abstract = {Tritium permeation through and retention in fusion reactor structures may be strongly influenced by the heat load carried by the structures through the Soret effect. After a short discussion suggestive of a heuristic model for predicting the associated energy and the heat of transport, data from several experiments are analyzed to show that the simplistic model works reasonably well with endothermic materials such as Fe and Ni, but is less successful with hydride formers. The implications of the model for tritium permeation and retention are discussed, and sample calculations are presented to illustrate the importance of properly accounting for the Soret effect in predicting tritium permeation and retention in fusion reactor structures. Neglecting the Soret effect may result in order of magnitude errors in estimating permeation and retention, while accounting for temperature sensitivity in the heat of transport will result in less significant corrections. An Appendix summarizes the development of transport equations from non-equilibrium thermodynamics to clarify the relationships between the various transport parameters involved.}, language = {en}, - number = {2P2}, - urldate = {2021-12-27}, - journal = {Fusion Technology}, - author = {Busigin, A. and Sood, S.K. and Kveton, O.K.}, + number = {1}, + urldate = {2019-10-25}, + journal = {Journal of Nuclear Materials}, + author = {Longhurst, Glen R.}, month = mar, - year = {1992}, - pages = {915--920}, - file = {Busigin et al. - 1992 - Dynamic Simulation of the ITER Fuel Cycle.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JRG2F4R4\\Busigin et al. - 1992 - Dynamic Simulation of the ITER Fuel Cycle.pdf:application/pdf}, + year = {1985}, + pages = {61--69}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\86GHHQVC\\Longhurst - 1985 - The soret effect and its implications for fusion r.pdf:application/pdf}, } -@article{glugla_tritium_2001, - title = {The tritium fuel cycle of {ITER}-{FEAT}}, - volume = {58-59}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379601003568}, - doi = {10.1016/S0920-3796(01)00356-8}, - abstract = {The Tritium Plant of ITER-FEAT is essential for the operation of the machine after the initial hydrogen phase, as tritium will be produced from DD fusion reactions. Within the fuel cycle of the Tokamak deuterium and later also tritium will be provided to the Fuelling Systems, and the unburned DT fraction recovered from the exhaust gases. The design of the tritium fuel cycle has to be based upon well proven technology to assure the safe handling of tritium along with credible accountancy, low tritium inventory, low generation of wastes and a high reliability of all components throughout the lifetime of ITER-FEAT.}, - language = {en}, - urldate = {2021-12-27}, - journal = {Fusion Engineering and Design}, - author = {Glugla, M and Busigin, A and Dörr, L and Haange, R and Hayashi, T and Kveton, O and Lässer, R and Murdoch, D. K and Nishi, M and Penzhorn, R. -D and Yoshida, H}, - month = nov, - year = {2001}, - keywords = {DD fusion, ITER-FEAT, Tritium fuel cycle, Tritium plant}, - pages = {349--353}, +@article{alimov_surface_2011, + title = {Surface morphology and deuterium retention in tungsten oxide layers exposed to low-energy, high flux {D} plasma}, + volume = {409}, + issn = {0022-3115}, + url = {http://www.sciencedirect.com/science/article/pii/S0022311510008500}, + doi = {10.1016/j.jnucmat.2010.12.028}, + abstract = {Surface morphology and deuterium retention in tungsten oxide layers (WO3−z, z⩽0.25) grown on polycrystalline and recrystallized W substrates have been examined after exposure to a low-energy (38eV/D), high flux (1022D/m2s) D plasma to an ion fluence of 1026D/m2 at various temperatures (up to ∼700K). Characterization methods used were scanning electron microscopy, X-ray diffraction, Rutherford backscattering spectroscopy, and the D(3He,p)4He nuclear reaction analysis. During exposure to the D plasma at temperatures of 340–615K, a partial reduction of the tungsten oxide takes place in the near-surface layer up to 0.3μm in depth. Even at around room temperature, deuterium atoms diffuse several micrometers into the tungsten oxide. The high D concentration of about 0.1D/W observed in the first micrometers below the surface at temperatures below 500K can be related mainly to D atoms chemically bonded to O atoms. As the exposure temperature increases, the D concentration decreases, reaching about 2×10−4D/W at 615K. At plasma exposure temperatures of about 700K, the oxide layer shrinks and loses a large fraction of oxygen.}, + number = {1}, + urldate = {2019-10-07}, + journal = {Journal of Nuclear Materials}, + author = {Alimov, V. K. and Tyburska, B. and Balden, M. and Lindig, S. and Roth, J. and Isobe, K. and Yamanishi, T.}, + month = feb, + year = {2011}, + pages = {27--32}, + file = {Alimov et al. - 2011 - Surface morphology and deuterium retention in tung.pdf:D\:\\Logiciels\\data_zotero\\storage\\V8JAGRHW\\Alimov et al. - 2011 - Surface morphology and deuterium retention in tung.pdf:application/pdf}, } -@article{cristescu_iter_2005, - title = {{ITER} {Dynamic} {Tritium} {Inventory} {Modeling} {Code}}, - volume = {48}, - issn = {1536-1055, 1943-7641}, - url = {https://www.tandfonline.com/doi/full/10.13182/FST05-A939}, - doi = {10.13182/FST05-A939}, - language = {en}, - number = {1}, - urldate = {2021-12-27}, - journal = {Fusion Science and Technology}, - author = {Cristescu, Ioana-R. and Dörr, L. and Busigin, A. and Murdoch, D.}, - month = aug, - year = {2005}, - pages = {343--348}, - file = {Cristescu et al. - 2005 - ITER Dynamic Tritium Inventory Modeling Code.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QK63IACZ\\Cristescu et al. - 2005 - ITER Dynamic Tritium Inventory Modeling Code.pdf:application/pdf}, +@article{inouye_hydrogen_2009, + series = {Proceedings of the 16th {International} {Conference} on {Ion} {Beam} {Modification} of {Materials}}, + title = {Hydrogen retention induced by ion implantation in tungsten trioxide films}, + volume = {267}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X09001165}, + doi = {10.1016/j.nimb.2009.01.139}, + abstract = {The relation between hydrogen retention and optical properties of an amorphous tungsten trioxide (WO3) film was investigated using 10keV H2+ ion implantation. WO3 films (350nm) covered by W layers (200nm) were deposited on SiO2 glass substrates by sputtering in a mixture of Ar and O2 gases. The hydrogen concentration in the WO3 film was characterized by elastic recoil detection analysis (ERDA). The hydrogen concentration in the WO3 film increased by 0.4 H/W in proportion to the fluence of the H2+ ions implanted into the W layer. The optical absorption coefficient of the film at 750nm increased linearly by 3μm−1 with an increase in the concentration of the implanted hydrogen up to 0.1 H/W, and saturated at 4μm−1 with the concentration higher than 0.1 H/W. These results indicate that the introduced hydrogen up to a hydrogen concentration of 0.1 H/W can be monitored by measuring the optical absorbance in the WO3 films.}, + number = {8}, + urldate = {2019-10-07}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Inouye, Aichi and Yamamoto, Shunya and Nagata, Shinji and Yoshikawa, Masahito and Shikama, Tatsuo}, + month = may, + year = {2009}, + pages = {1480--1483}, + file = {Inouye et al. - 2009 - Hydrogen retention induced by ion implantation in .pdf:D\:\\Logiciels\\data_zotero\\storage\\E88X9A75\\Inouye et al. - 2009 - Hydrogen retention induced by ion implantation in .pdf:application/pdf}, } -@article{you_european_2018, - title = {European divertor target concepts for {DEMO}: {Design} rationales and high heat flux performance}, - volume = {16}, - issn = {2352-1791}, - shorttitle = {European divertor target concepts for {DEMO}}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179118300437}, - doi = {10.1016/j.nme.2018.05.012}, - abstract = {The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating. For reliable exhaust of huge thermal power, robust and durable divertor target PFCs with a sufficiently large heat removal capability and lifetime has to be developed. Since 2014 in the framework of the preconceptual design activities of the EUROfusion DEMO project, integrated R\&D efforts have been made in the subproject ‘Target development’ of the work package ‘Divertor’ to develop divertor target PFCs for DEMO. Recently, the first R\&D phase was concluded where six (partly novel) target PFC concepts were developed and evaluated by means of non-destructive inspections and high-heat-flux fatigue testing. In this paper, the major achievements of the first phase activities in this subproject are presented focusing on the design rationales of the target PFC concepts, technology options employed for small-scale mock-up fabrication and the results of the first round high-heat-flux qualification test campaign. It is reported that the mock-ups of three PFC concepts survived up to 500 loading cycles at 20 MW/m² (with hot water cooling at 130 °C) without any discernable indication of degradation in performance or structural integrity.}, - language = {en}, - urldate = {2021-12-22}, - journal = {Nuclear Materials and Energy}, - author = {You, J. H. and Visca, E. and Barrett, T. and Böswirth, B. and Crescenzi, F. and Domptail, F. and Fursdon, M. and Gallay, F. and Ghidersa, B-E. and Greuner, H. and Li, M. and Müller, A. v. and Reiser, J. and Richou, M. and Roccella, S. and Vorpahl, Ch.}, - month = aug, - year = {2018}, - keywords = {DEMO, EUROfusion, Composites, Divertor targets, High-heat-flux, Plasma-facing component}, - pages = {1--11}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2MSX7RJF\\You et al. - 2018 - European divertor target concepts for DEMO Design.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MDAWITGD\\S2352179118300437.html:text/html;Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IIX5LQ7G\\You et al. - 2018 - European divertor target concepts for DEMO Design.pdf:application/pdf}, +@article{nagata_hydrogen_2007, + series = {Proceedings of the {International} {Symposium} on {Metal}-{Hydrogen} {Systems}, {Fundamentals} and {Applications} ({MH2006})}, + title = {Hydrogen incorporation and gasochromic coloration of tungsten oxide films}, + volume = {446-447}, + issn = {0925-8388}, + url = {http://www.sciencedirect.com/science/article/pii/S0925838807000886}, + doi = {10.1016/j.jallcom.2007.01.039}, + abstract = {The retention and release of hydrogen were studied in connection with the gasochromic coloration and bleaching of tungsten oxide (WO3) thin films prepared by RF magnetron sputtering at various substrate temperatures. The concentration depth profiles of hydrogen in the WO3 film were measured by the Elastic Recoil Detection Analysis technique. The hydrogen was effectively incorporated and was uniformly distributed in the WO3 films deposited at the higher substrate temperatures above 400K, where crystalline structure was formed with a preferred orientation. Excellent gasochromic characteristics were found for the highly oriented crystalline WO3 film covered with a Pd layer. In situ measurements of hydrogen retention and optical transmission of the WO3 demonstrated that hydrogen concentration in the WO3 film increased with decreasing the optical transmission during the exposure of hydrogen gas.}, + urldate = {2019-10-07}, + journal = {Journal of Alloys and Compounds}, + author = {Nagata, S. and Inouye, A. and Yamamoto, S. and Tsuchiya, B. and Takano, K. and Toh, K. and Shikama, T.}, + month = oct, + year = {2007}, + pages = {558--561}, + file = {Nagata et al. - 2007 - Hydrogen incorporation and gasochromic coloration .pdf:D\:\\Logiciels\\data_zotero\\storage\\BK8BFPSE\\Nagata et al. - 2007 - Hydrogen incorporation and gasochromic coloration .pdf:application/pdf}, } -@article{domptail_design_2020, - title = {The design and optimisation of a monoblock divertor target for {DEMO} using thermal break interlayer}, - volume = {154}, +@article{heuer_aiming_2018, + title = {Aiming at understanding thermo-mechanical loads in the first wall of {DEMO}: {Stress}–strain evolution in a {Eurofer}-tungsten test component featuring a functionally graded interlayer}, + volume = {135}, issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379620300454}, - doi = {10.1016/j.fusengdes.2020.111497}, - abstract = {A high performing DEMO divertor target mock-up design that uses the thermal break interlayer concept is presented. The design evolved from a previous design of which six mock-ups were designed, fabricated and subjected to high heat flux testing. The new design was generated using optimisation techniques; specifically, software was developed to automatically process the design of experiments data to enable visualisation of the design space. Despite the more challenging geometric constraints of this second phase, this design performs significantly better than that of the previous phase; the strain in the interlayer, which was the dominant damage mode in the phase 1 testing, is reduced by 28\%. Four mock-ups of the selected design were manufactured, all of which successfully passed a series of high heat flux testing, including 500 cycles at 20 MW/m2. Design optimisation methods are not widely utilised in fusion engineering, their potential benefits, which are demonstrated here on a plasma facing component, could be applied to many other challenging designs.}, + shorttitle = {Aiming at understanding thermo-mechanical loads in the first wall of {DEMO}}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618305660}, + doi = {10.1016/j.fusengdes.2018.07.011}, + abstract = {For the future fusion demonstration power plant, DEMO, several blanket designs are currently under consideration. Despite geometric and operational differences, all designs suggest a first wall (FW), in which tungsten (W) armour is joined to a structure made of Reduced Activation Ferritic Martensitic (RAFM) steel. In thermo-mechanical analyses of breeding blankets, this joint has received limited attention. In order to provide a basis for better understanding of thermally induced stresses and strains in the FW, the thermo-mechanical behaviour of a water-cooled test component is explored in the current contribution. The model aims at providing a simple geometry that allows straightforward comparison of numerical and experimental results, while trying to keep boundary conditions as realistic as possible. A test component with direct RAFM steel-W joint, and a test component with a stress-redistributing, functionally graded RAFM steel/W interlayer in the joint is considered in the current contribution. The analyses take production- and operation-related loads into account. Following a detailed analysis of the evolution of stress components and strain in the model, a parameter study with respect to geometric specifications and loads is presented. The analyses show that, even in a small test component, a direct RAFM steel-W joint causes enormous plastic deformation. The implementation of a functionally graded interlayer reduces stresses and strains significantly, but vertical normal stresses at the joint's circumference remain considerable. With the component geometry considered here, the graded interlayer should be at least 1 mm thick and contain 4 sublayers to appropriately redistribute stresses. Beyond a component width of 14 mm, stresses increase strongly, which may pose a risk to the applicability of large-scale FW components, too.}, language = {en}, - urldate = {2021-12-22}, + urldate = {2019-10-25}, journal = {Fusion Engineering and Design}, - author = {Domptail, F. and Barrett, T. R. and Fursdon, M. and Lukenskas, A. and You, J-H.}, - month = may, - year = {2020}, - keywords = {DEMO, High heat flux, Design optimisation, Divertor target, Thermal break}, - pages = {111497}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9MP3TG8C\\S0920379620300454.html:text/html;Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6T3IFVCD\\Domptail et al. - 2020 - The design and optimisation of a monoblock diverto.pdf:application/pdf}, + author = {Heuer, S. and Weber, Th. and Pintsuk, G. and Coenen, J. W. and Matejicek, J. and Linsmeier, Ch.}, + month = oct, + year = {2018}, + pages = {141--153}, + file = {Heuer et al. - 2018 - Aiming at understanding thermo-mechanical loads in.pdf:D\:\\Logiciels\\data_zotero\\storage\\YUS6HWPT\\Heuer et al. - 2018 - Aiming at understanding thermo-mechanical loads in.pdf:application/pdf}, } -@article{gilardi_comparison_2021, - title = {Comparison of two modelling tools for the evaluation of tritium and hydrogen transfers in nuclear reactors or complex systems}, - volume = {166}, - issn = {09203796}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379621000545}, - doi = {10.1016/j.fusengdes.2021.112278}, - abstract = {In the framework of the TRANSAT project, started in 2017 (TRANSversal Actions for Tritium supported within the H2020 Euratom program), the ability to measure and to assess the tritium inventory and migration within different kinds of reactors or processes is one major challenge to control the potential releases and personal dosimetry in nominal operating conditions.}, +@article{delaporte-mathurin_finite_2019, + title = {Finite element analysis of hydrogen retention in {ITER} plasma facing components using {FESTIM}}, + volume = {21}, + copyright = {All rights reserved}, + issn = {2352-1791}, + url = {http://www.sciencedirect.com/science/article/pii/S2352179119300547}, + doi = {10.1016/j.nme.2019.100709}, + abstract = {The behaviour of hydrogen isotopes in ITER monoblocks was studied using the code FESTIM (Finite Element Simulation of Tritium In Materials) which is introduced in this publication. FESTIM has been validated by reproducing experimental data and the Method of Manufactured Solutions was used for analytical verification. Following relevant plasma scenarios, both transient heat transfer and hydrogen isotopes (HIs) diffusion have been simulated in order to assess HIs retention in monoblocks. Relevant materials properties have been used. Each plasma cycle is composed of a current ramp up, a current plateau, a current ramp down and a resting phase before the following shot. 100 cycles are simulated. The total HIs inventory in the tokamak during resting phases reaches 1.8×10−3mg whereas during the implantation phases it keeps increasing as a power law of time. Particle flux on the cooling channel of the monoblock is also computed. The breakthrough time is estimated to be t=1×105s which corresponds to 24 cycles. Relevance of 2D modelling has been demonstrated by comparing the total HIs inventory obtained by 2D and 1D simulations. Using 1D simulations, a relative error is observed compared to 2D simulations which can reach -25\% during the resting phase. The error during implantation phases keeps increasing.}, language = {en}, - urldate = {2021-12-17}, + urldate = {2019-10-23}, + journal = {Nuclear Materials and Energy}, + author = {Delaporte-Mathurin, Rémi and Hodille, Etienne A. and Mougenot, Jonathan and Charles, Yann and Grisolia, Christian}, + month = dec, + year = {2019}, + pages = {100709}, + file = {Delaporte-Mathurin et al. - 2019 - Finite element analysis of hydrogen retention in I.pdf:D\:\\Logiciels\\data_zotero\\storage\\7SS9QGWF\\Delaporte-Mathurin et al. - 2019 - Finite element analysis of hydrogen retention in I.pdf:application/pdf}, +} + +@article{durif_impact_2019, + title = {Impact of tungsten recrystallization on {ITER}-like components for lifetime estimation}, + volume = {138}, + issn = {0920-3796}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379618307026}, + doi = {10.1016/j.fusengdes.2018.11.003}, + abstract = {For ITER divertor, plasma facing components are made with tungsten as armor material. In previous papers, it has been shown that plasma facing components are prone to crack, appearing in tungsten block during thermal cyclic heat loading. In order to predict component lifetime, a numerical simulation is proposed in this paper. With regard to previous studies, tungsten (raw and recrystallized) real mechanical behaviors are taken into account. To be used as inputs for numerical simulations, compressive tests at different temperatures and strain rates were realized on raw and recrystallized tungsten. Raw tungsten tests reveal a linear elastic and ideal plastic behavior that is sensitive to strain rate. Concerning recrystallized tungsten, an elastic-viscoplastic behavior is observed on the entire explored temperature range (up to 1150 °C), that can be described by an elastic-plastic model with kinematic hardening. Manson-Coffin relationships are used to estimate the lifetime. When taking into account real mechanical behaviors for raw tungsten and recrystallized tungsten, we show that lifetime estimation is mainly driven by recrystallized thickness in the component, by the ductile to brittle transition temperature and finally by strain rate.}, + urldate = {2019-10-07}, journal = {Fusion Engineering and Design}, - author = {Gilardi, T. and Moreno, C. and Grisolia, C.}, - month = may, - year = {2021}, - pages = {112278}, - file = {Gilardi et al. - 2021 - Comparison of two modelling tools for the evaluati.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DWJEZMR7\\Gilardi et al. - 2021 - Comparison of two modelling tools for the evaluati.pdf:application/pdf}, + author = {Durif, A. and Richou, M. and Kermouche, G. and Lenci, M. and Bergheau, J-M.}, + month = jan, + year = {2019}, + pages = {247--253}, + file = {Durif et al. - 2019 - Impact of tungsten recrystallization on ITER-like .pdf:D\:\\Logiciels\\data_zotero\\storage\\BMYRMN2V\\Durif et al. - 2019 - Impact of tungsten recrystallization on ITER-like .pdf:application/pdf}, } -@article{franza_tritium_2013, - title = {Tritium transport analysis in {HCPB} {DEMO} blanket with the {FUS}-{TPC} code}, - volume = {88}, - issn = {09203796}, - url = {https://linkinghub.elsevier.com/retrieve/pii/S0920379613004857}, - doi = {10.1016/j.fusengdes.2013.05.045}, - language = {en}, - number = {9-10}, - urldate = {2021-12-17}, - journal = {Fusion Engineering and Design}, - author = {Franza, F. and Boccaccini, L.V. and Ciampichetti, A. and Zucchetti, M.}, - month = oct, - year = {2013}, - pages = {2444--2447}, - file = {Franza et al. - 2013 - Tritium transport analysis in HCPB DEMO blanket wi.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9CV3CLHU\\Franza et al. - 2013 - Tritium transport analysis in HCPB DEMO blanket wi.pdf:application/pdf}, +@article{ziegler_srim_2010, + series = {19th {International} {Conference} on {Ion} {Beam} {Analysis}}, + title = {{SRIM} – {The} stopping and range of ions in matter (2010)}, + volume = {268}, + issn = {0168-583X}, + url = {http://www.sciencedirect.com/science/article/pii/S0168583X10001862}, + doi = {10.1016/j.nimb.2010.02.091}, + abstract = {SRIM is a software package concerning the Stopping and Range of Ions in Matter. Since its introduction in 1985, major upgrades are made about every six years. Currently, more than 700 scientific citations are made to SRIM every year. For SRIM-2010, the following major improvements have been made: (1) About 2800 new experimental stopping powers were added to the database, increasing it to over 28,000 stopping values. (2) Improved corrections were made for the stopping of ions in compounds. (3) New heavy ion stopping calculations have led to significant improvements on SRIM stopping accuracy. (4) A self-contained SRIM module has been included to allow SRIM stopping and range values to be controlled and read by other software applications. (5) Individual interatomic potentials have been included for all ion/atom collisions, and these potentials are now included in the SRIM package. A full catalog of stopping power plots can be downloaded at www.SRIM.org. Over 500 plots show the accuracy of the stopping and ranges produced by SRIM along with 27,000 experimental data points. References to the citations which reported the experimental data are included.}, + number = {11}, + urldate = {2019-10-07}, + journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, + author = {Ziegler, James F. and Ziegler, M. D. and Biersack, J. P.}, + month = jun, + year = {2010}, + pages = {1818--1823}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\YU9BMWW2\\Ziegler et al. - 2010 - SRIM – The stopping and range of ions in matter (2.pdf:application/pdf}, } -@techreport{chang_h_oh_development_2009, - title = {Development and {Verification} of {Tritium} {Analyses} {Code} for a {Very} {High} {Temperature} {Reactor}}, - url = {http://www.osti.gov/servlets/purl/969495-ytycuv/}, +@article{ueda_baseline_2017, + title = {Baseline high heat flux and plasma facing materials for fusion}, + volume = {57}, + issn = {0029-5515}, + url = {https://doi.org/10.1088%2F1741-4326%2Faa6b60}, + doi = {10.1088/1741-4326/aa6b60}, + abstract = {In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).}, language = {en}, - number = {INL/EXT-09-16743, 969495}, - urldate = {2021-12-17}, - author = {{Chang H. Oh} and {Eung S. Kim}}, - month = sep, - year = {2009}, - doi = {10.2172/969495}, - pages = {INL/EXT--09--16743, 969495}, - file = {Chang H. Oh et Eung S. Kim - 2009 - Development and Verification of Tritium Analyses C.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NK8GYRN2\\Chang H. Oh et Eung S. Kim - 2009 - Development and Verification of Tritium Analyses C.pdf:application/pdf}, + number = {9}, + urldate = {2019-10-07}, + journal = {Nuclear Fusion}, + author = {Ueda, Y. and Schmid, K. and Balden, M. and Coenen, J. W. and Loewenhoff, Th and Ito, A. and Hasegawa, A. and Hardie, C. and Porton, M. and Gilbert, M.}, + month = jun, + year = {2017}, + pages = {092006}, + file = {Ueda et al. - 2017 - Baseline high heat flux and plasma facing material.pdf:D\:\\Logiciels\\data_zotero\\storage\\TAUSS4CR\\Ueda et al. - 2017 - Baseline high heat flux and plasma facing material.pdf:application/pdf}, } -@article{thompson_identifying_2021, - title = {Identifying microstructural changes responsible for retarded grain growth during tungsten recrystallization after helium plasma exposure}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311521006681}, - doi = {10.1016/j.jnucmat.2021.153448}, - abstract = {Helium plasma is known to affect recrystallization in tungsten, with lower temperatures during plasma exposure leading to slower crystal grain growth. To understand why this occurs, tungsten samples were first exposed to helium plasma at surface temperatures between 300°C and 800°C, before annealing at temperatures between 1100°C and 1400°C. Annealing after helium exposure at 300°C was confirmed to lead to smaller crystal grains than annealing after exposure to helium at 500°C. Small 1-2 nm radius nanobubbles formed readily in tungsten after helium plasma exposure, but disappear after annealing at temperatures of 1100°C and above. The formation of cracks and open volumes beneath the surface was observed exclusively in tungsten exposed to helium-plasma at 300°C, with extensive surface cracks visible after annealing. These cracks were not observed for higher temperature helium exposure and likely form due to the strong tendency of bubbles to cluster along grain boundaries for helium exposure at 300°C. Despite this, nano-mechanical testing revealed a similar influence of annealing conditions on tungsten hardness for all plasma exposure conditions studied. The crack formation is likely caused by interactions between solute helium and residual defects from surface polishing.}, +@article{roache_code_2002, + title = {Code {Verification} by the {Method} of {Manufactured} {Solutions}}, + volume = {124}, + issn = {0098-2202}, + url = {https://asmedigitalcollection.asme.org/fluidsengineering/article/124/1/4/462791/Code-Verification-by-the-Method-of-Manufactured}, + doi = {10.1115/1.1436090}, language = {en}, - urldate = {2021-12-12}, - journal = {Journal of Nuclear Materials}, - author = {Thompson, M. A. T. and Song, K. and De Temmerman, G. and Chen, H. and Kirby, N. and Bradby, J. and Bhattacharyya, D. and Hoang, Calvin and Corr, C. S.}, - month = dec, - year = {2021}, - pages = {153448}, -} - -@article{nguyen_developpement_nodate, - title = {Développement d'outils numériques pour la prise en compte du couplage hydrogène-plasticité dans un code éléments finis: application à l'essai de pliage en {U}}, - language = {fr}, - author = {Nguyen, Tuan Hung}, - pages = {165}, - file = {Nguyen - Développement d'outils numériques pour la prise en.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QN59NR8P\\Nguyen - Développement d'outils numériques pour la prise en.pdf:application/pdf}, + number = {1}, + urldate = {2019-10-07}, + journal = {Journal of Fluids Engineering}, + author = {Roache, Patrick J.}, + month = mar, + year = {2002}, + pages = {4--10}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\RQV38CGQ\\Code-Verification-by-the-Method-of-Manufactured.html:text/html}, } -@article{kembleton_eu-demo_2022, - title = {{EU}-{DEMO} design space exploration and design drivers}, - volume = {178}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379622000801}, - doi = {10.1016/j.fusengdes.2022.113080}, - abstract = {Once the high-level requirements for a fusion power plant are set, the expected performance of plant systems, including the plasma, must be defined and then the available design space for the plant can be explored in order to converge on a final overall plant operating point, setting the major plant parameters such as number of toroidal field (TF) coils, tokamak major radius, plant power flows etc. Such design space explorations are conducted using systems codes which contain simplified models for plant systems, and attempt to capture the interactions between them in order to balance performance trade-offs and enforce overall consistency. This paper summarizes the work carried out to identify the EU-DEMO baseline operating point and the underpinning assumptions about technology and physics performance. The major design choices are described and the principle drivers for the direction of conceptual development, resulting in the operating space for EU-DEMO, are identified. The final output of the systems code forms the basis for more detailed engineering and physics evaluation and design work.}, - language = {en}, - urldate = {2022-03-15}, - journal = {Fusion Engineering and Design}, - author = {Kembleton, R. and Morris, J. and Siccinio, M. and Maviglia, F.}, - month = may, - year = {2022}, - keywords = {Systems code, EU-DEMO, Physics and engineering basis, Reactor}, - pages = {113080}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I4JE54I8\\Kembleton et al. - 2022 - EU-DEMO design space exploration and design driver.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\D4VNH3JK\\S0920379622000801.html:text/html}, +@article{dudson_verification_2016, + title = {Verification of {BOUT}++ by the method of manufactured solutions}, + volume = {23}, + issn = {1070-664X}, + url = {https://aip.scitation.org/doi/10.1063/1.4953429}, + doi = {10.1063/1.4953429}, + number = {6}, + urldate = {2019-10-07}, + journal = {Physics of Plasmas}, + author = {Dudson, B. D. and Madsen, J. and Omotani, J. and Hill, P. and Easy, L. and Løiten, M.}, + month = jun, + year = {2016}, + pages = {062303}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QZENTZAZ\\1.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\XXIKJDVY\\Dudson et al. - 2016 - Verification of BOUT++ by the method of manufactur.pdf:application/pdf}, } -@article{liu_hydrogen_2014, - series = {Proceedings of the 16th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-16)}, - title = {Hydrogen diffusion in tungsten: {A} molecular dynamics study}, - volume = {455}, - issn = {0022-3115}, - shorttitle = {Hydrogen diffusion in tungsten}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311514005911}, - doi = {10.1016/j.jnucmat.2014.09.003}, - abstract = {The diffusion behavior of hydrogen (H) in tungsten (W) has been studied by molecular dynamics simulations. The diffusivities from 200K to 3000K are calculated and the diffusion equation is fitted to D=5.13×10−8exp(−0.21eV/kT)m2/s. The diffusion equations in different temperature ranges of 200–500K, 500–2400K and 2400–3000K are also given separately and the results imply different H diffusion modes in different temperature ranges, which is proved by analyzing equilibrium H positions at low and high temperatures. The H atom jumps between different tetrahedral interstitial sites (TISs) at lower temperatures, but the transition to octahedral interstitial sites (OISs) is also observed at high temperatures. Moreover, with a vacancy present in the W system, vacancy trapping of H is observed, and it is shown that the vacancy trapping reduces with the increasing temperature. The H binding energy to monovacancy is obtained using three different methods including NEB and fitting both H diffusivity and time for H to detrap from the vacancy, which provides more information of the H behaviors with the existence of defects.}, - language = {en}, +@article{longhurst_verification_2005, + title = {Verification and {Validation} of the {Tritium} {Transport} {Code} {TMAP7}}, + volume = {48}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST05-A967}, + doi = {10.13182/FST05-A967}, + abstract = {The TMAP code has been upgraded to version 7, which includes radioactive decay along with many features implemented in prior versions. Pursuant to acceptance and release for distribution, the code was exercised in a variety of problem types to demonstrate that it provides results in agreement with theoretical results for cases where those are available. It has also been used to model certain experimental results. In this paper, the capabilities of the TMAP7 code are demonstrated by presenting some of the results from the verification and validation process.}, number = {1}, - urldate = {2022-03-15}, - journal = {Journal of Nuclear Materials}, - author = {Liu, Yi-Nan and Wu, Tiefeng and Yu, Yi and Li, Xiao-Chun and Shu, Xiaolin and Lu, Guang-Hong}, - month = dec, - year = {2014}, - keywords = {molecular dynamics}, - pages = {676--680}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XAHNCMLY\\S0022311514005911.html:text/html}, + urldate = {2019-10-07}, + journal = {Fusion Science and Technology}, + author = {Longhurst, Glen R. and Ambrosek, James}, + month = aug, + year = {2005}, + pages = {468--471}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QU7HWSBA\\FST05-A967.html:text/html}, } -@article{wang_molecular_2020, - title = {Molecular dynamics studies of hydrogen diffusion in tungsten at elevated temperature: {Concentration} dependence and defect effects}, - volume = {45}, - issn = {0360-3199}, - shorttitle = {Molecular dynamics studies of hydrogen diffusion in tungsten at elevated temperature}, - url = {https://www.sciencedirect.com/science/article/pii/S0360319919339989}, - doi = {10.1016/j.ijhydene.2019.10.151}, - abstract = {Influence of hydrogen concentration and defects introduced by neutron irradiation on hydrogen diffusion in tungsten has been investigated by molecular dynamics simulation at elevated temperatures. Hydrogen diffusion is shown to be significantly restrained at high concentrations due to spontaneous formation of platelet-like hydrogen clusters. For neutron irradiation defects, self-interstitials, mono-vacancies and vacancy clusters are considered. By clustering and acting as dislocation loops, self-interstitials show considerable trapping effects on hydrogen, leading to the suppression of hydrogen effective diffusion and the change of diffusion model in which hydrogen mainly diffuses along dislocation lines instead of hopping between tetrahedral interstitial sites. Moreover, an equation connecting hydrogen diffusion parameters and the total length of dislocation loops is empirically established. Different influences of mono-vacancies and vacancy clusters on hydrogen diffusion have been carefully identified. With the same vacancy concentration, hydrogen diffusivity is lower with mono-vacancies than that with vacancy clusters because more isolated trapping sites are provided by mono-vacancies. This work is not only helpful for understanding the synergistic effects of neutron irradiation and plasma interaction, but also potentially applicable for larger scale simulations as input data.}, - language = {en}, +@article{blondel_modeling_2017, + title = {Modeling {Helium} {Segregation} to the {Surfaces} of {Plasma}-{Exposed} {Tungsten} as a {Function} of {Temperature} and {Surface} {Orientation}}, + volume = {71}, + issn = {1536-1055}, + url = {https://doi.org/10.13182/FST16-112}, + doi = {10.13182/FST16-112}, + abstract = {We provide a description of the dependence on surface crystallographic orientation and temperature of the segregation of helium implanted with energies consistent with low-energy plasma exposure to tungsten surfaces. Here, we describe multiscale modeling results based on a hierarchical approach to scale bridging that incorporates atomistic studies based on a reliable interatomic potential to parameterize a spatially dependent drift-diffusion-reaction cluster-dynamics code. An extensive set of molecular dynamics (MD) simulations has been performed at 933 K and/or 1200 K to determine the probabilities of desorption and modified trap mutation that occurs as small, mobile Hen (1 ≤ n ≤ 7) clusters diffuse from the near-surface region toward surfaces of varying crystallographic orientation due to an elastic interaction force that provides the thermodynamic driving force for surface segregation. These near-surface cluster dynamics have significant effects on the surface morphology, the near-surface defect structures, and the amount of helium retained in the material upon plasma exposure, for which we have developed an extensive MD database of cumulative evolution during high-flux helium implantation at 933 K, which we compare to our properly parameterized cluster-dynamics model. This validated model is then used to evaluate the effects of temperature on helium retention and subsurface helium clustering.}, number = {1}, - urldate = {2022-03-15}, - journal = {International Journal of Hydrogen Energy}, - author = {Wang, Li-Fang and Shu, Xiaolin and Lin, De-Ye and Lu, Guang-Hong and Song, Hai-Feng}, + urldate = {2019-10-07}, + journal = {Fusion Science and Technology}, + author = {Blondel, Sophie and Hammond, Karl D. and Hu, Lin and Maroudas, Dimitrios and Wirth, Brian D.}, month = jan, - year = {2020}, - keywords = {Tungsten, Hydrogen diffusion, Molecular dynamics, Irradiation defect}, - pages = {822--834}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GDC7BPBN\\S0360319919339989.html:text/html}, + year = {2017}, + pages = {22--35}, } -@article{einstein_uber_1905, - title = {Über die von der molekularkinetischen {Theorie} der {Wärme} geforderte {Bewegung} von in ruhenden {Flüssigkeiten} suspendierten {Teilchen}}, - volume = {322}, - issn = {1521-3889}, - url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/andp.19053220806}, - doi = {10.1002/andp.19053220806}, - language = {en}, - number = {8}, - urldate = {2022-03-15}, - journal = {Annalen der Physik}, - author = {Einstein, A.}, - year = {1905}, - note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1002/andp.19053220806}, - pages = {549--560}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I5VFVCTF\\Einstein - 1905 - Über die von der molekularkinetischen Theorie der .pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZNHJEGNF\\andp.html:text/html}, +@misc{gallo_surface_2014, + type = {Laurea {Magistrale} / {Specialistica}}, + title = {Surface modifications and deuterium retention of tungsten and tungsten oxide thin films after high flux deuterium plasma exposure}, + url = {https://www.politesi.polimi.it/handle/10589/94446}, + abstract = {PASSONI, MATTEO}, + language = {eng}, + urldate = {2019-10-07}, + author = {GALLO, ALBERTO}, + month = jul, + year = {2014}, } -@article{behler_constructing_2015, - title = {Constructing high-dimensional neural network potentials: {A} tutorial review}, - volume = {115}, - issn = {00207608}, - shorttitle = {Constructing high-dimensional neural network potentials}, - url = {https://onlinelibrary.wiley.com/doi/10.1002/qua.24890}, - doi = {10.1002/qua.24890}, - language = {en}, - number = {16}, - urldate = {2022-03-18}, - journal = {International Journal of Quantum Chemistry}, - author = {Behler, Jörg}, - month = aug, - year = {2015}, - pages = {1032--1050}, - file = {Behler - 2015 - Constructing high-dimensional neural network poten.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HDVEB9KR\\Behler - 2015 - Constructing high-dimensional neural network poten.pdf:application/pdf}, +@phdthesis{addab_formation_2016, + type = {thesis}, + title = {Formation, caractérisation et bombardements ioniques de films minces de {WO3} d'intérêt pour la fusion magnétique}, + url = {http://www.theses.fr/2016AIXM4765}, + abstract = {Dans ce travail, nous étudions la stabilité thermique et les effets des irradiations par un plasma d'hélium ou de deutérium de films minces de WO3 d’intérêt pour la fusion magnétique (projet ITER). L’objectif est de comprendre comment une oxydation du divertor modifie les interactions plasma paroi. Pour cela, nous avons synthétisé des films de WO3 par oxydation thermique de substrats de W à 400°C et caractérisé les effets du type de substrat, de la pression d’oxygène et du temps d’oxydation sur la structure et sur l’épaisseur des oxydes formés. La structure (monoclinique nanocristalline), la morphologie et les défauts des échantillons ont été analysés avant et après traitement, à différentes échelles, en utilisant la microscopie électronique, la microscopie Raman, la diffraction de rayons X, et la microscopie à force atomique.Le chauffage sous vide (400 - 800°C) a conduit à la formation de WO2. Le bombardement aux ions D+ (11 eV) a mené à une diffusion profonde du deutérium à travers le film d’oxyde, engendrant un effet électrochimique, observé ici pour la première fois sous irradiation plasma. Cet effet, réversible, est associé à la formation de bronzes de tungstène (DxWO3) et à une transition de phase vers une structure hexagonale. Des bombardements aux ions He+ (20 eV) ont été réalisés afin de dissocier les effets physiques et chimiques. A température ambiante, le bombardement a causé peu de changements morphologiques et structuraux. Par contre, le autre bombardement à 400°C a causé une érosion du film d’oxyde accompagnée d’un changement de couleur, une amorphisation en surface et la formation de bulles à l’interface W / WO3.}, + urldate = {2019-10-07}, + school = {Aix-Marseille}, + author = {Addab, Younes}, + month = dec, + year = {2016}, + file = {Addab - 2016 - Formation, caractérisation et bombardements ioniqu.pdf:D\:\\Logiciels\\data_zotero\\storage\\6RMYKZ58\\Addab - 2016 - Formation, caractérisation et bombardements ioniqu.pdf:application/pdf}, } -@article{henriksson_difference_2005, - title = {Difference in formation of hydrogen and helium clusters in tungsten}, - volume = {87}, - issn = {0003-6951, 1077-3118}, - url = {http://aip.scitation.org/doi/10.1063/1.2103390}, - doi = {10.1063/1.2103390}, - language = {en}, - number = {16}, - urldate = {2022-03-16}, - journal = {Applied Physics Letters}, - author = {Henriksson, K. O. E. and Nordlund, K. and Krasheninnikov, A. and Keinonen, J.}, - month = oct, - year = {2005}, - pages = {163113}, - file = {Henriksson et al. - 2005 - Difference in formation of hydrogen and helium clu.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MAN8CDTS\\Henriksson et al. - 2005 - Difference in formation of hydrogen and helium clu.pdf:application/pdf}, +@inproceedings{huang_tungsten_2016, + title = {Tungsten monoblock concepts for the {FNSF} first wall and divertor}, + abstract = {Next-step fusion nuclear devices require plasma-facing components that can survive a much higher neutron dose than ITER, and in many design concepts also require higher operating temperatures, higher reliability, and materials with more attractive safety and environmental characteristics. In search of first wall concepts that can withstand surface heat fluxes beyond 2 MW/m, we analyzed advanced “monoblock” designs using coolants and materials that offer more attractive long-term performance. These use tungsten armor and heat sinks, similar to previous designs, but replace the coolant with helium and the coolant containment pipe with either low-activation ferritic-martensitic steel or SiC/SiC composite. The results of analysis show that helium-cooled steel can remove up to 5 MW/m of steady-state surface heat flux and helium-cooled SiC/SiC can remove nearly 10 MW/m while satisfying all materials and design requirements. This suggests that a He-cooled W/SiC monoblock could withstand divertor-like heat fluxes.}, + author = {Huang, Yan and Tillack, Mark S. and Ghoniem, Nasr M.}, + year = {2016}, + file = {Huang et al. - 2016 - Tungsten monoblock concepts for the FNSF first wal.pdf:D\:\\Logiciels\\data_zotero\\storage\\MGSBJ3Z9\\Huang et al. - 2016 - Tungsten monoblock concepts for the FNSF first wal.pdf:application/pdf}, +} + +@article{crescenzi_iter-like_2017, + series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, + title = {{ITER}-like divertor target for {DEMO}: {Design} study and fabrication test}, + volume = {124}, + issn = {0920-3796}, + shorttitle = {{ITER}-like divertor target for {DEMO}}, + url = {http://www.sciencedirect.com/science/article/pii/S0920379617300972}, + doi = {10.1016/j.fusengdes.2017.02.014}, + abstract = {As a major in-vessel component of a tokamak-type fusion reactor, the divertor is mainly in charge of removal of particles and partial power exhaust via scrape-off layer. The target plate of the divertor is directly exposed to non-uniform high heat flux on the surface by particle bombardment and radiation. In the case of ITER and a DEMO reactor, the peak surface heat flux is expected to reach up to 10MW/m2 during normal operation and 20MW/m2 during slow transient events like loss of plasma detachment. This paper reports the results of a preliminary code-based design study and fabrication technology verification test which were conducted for developing an ITER-like divertor target design for the DEMO divertor. The structural failure evaluation against the ratchetting and fatigue criteria of the ITER SDC-IC showed that the design with reduced dimensions would allow sufficient design margin (reserve factor) for three distinct thermal loading cases. The first trial of mock-up fabrication using a new joining furnace at ENEA was successfully completed. The ultrasonic inspection test made before and after the cyclic HHF tests at GLADIS facility demonstrated high quality of fabrication and robust design concept.}, + urldate = {2019-10-07}, + journal = {Fusion Engineering and Design}, + author = {Crescenzi, F. and Greuner, H. and Roccella, S. and Visca, E. and You, J. H.}, + month = nov, + year = {2017}, + pages = {432--436}, + file = {Crescenzi et al. - 2017 - ITER-like divertor target for DEMO Design study a.pdf:D\:\\Logiciels\\data_zotero\\storage\\L76P4XA7\\Crescenzi et al. - 2017 - ITER-like divertor target for DEMO Design study a.pdf:application/pdf}, } @article{haasz_effect_1999, @@ -8269,63 +8472,60 @@ @article{haasz_effect_1999 author = {Haasz, A. A. and Poon, M. and Davis, J. W.}, month = mar, year = {1999}, - keywords = {Tungsten, Hydrogen retention, Deuterium inventory, Ion implantation, Hydrogen trapping}, + keywords = {Tungsten, Hydrogen trapping, Deuterium inventory, Ion implantation, Hydrogen retention}, pages = {520--525}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\IDKPKZAY\\S0022311598005868.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\IDKPKZAY\\S0022311598005868.html:text/html}, } -@article{holzner_solute_2020, - title = {Solute diffusion of hydrogen isotopes in tungsten—a gas loading experiment}, - volume = {T171}, - issn = {1402-4896}, - url = {https://doi.org/10.1088/1402-4896/ab4b42}, - doi = {10.1088/1402-4896/ab4b42}, - abstract = {The diffusion of protium and deuterium in tungsten is measured in gas loading experiments as a function of temperature for a hydrogen isotope loading pressure of 500 mbar and temperatures between 1600 K and 2600 K. The diffusion parameters are measured from the degassing rates of both a single-crystalline and a polycrystalline tungsten cylinder by mass spectrometry. The data are analysed assuming an Arrhenius-like temperature dependence of the diffusivity and following the classical analysis approach of Frauenfelder (1969 J. Vac Sci. Technol. 6, 388). For deuterium in tungsten an activation energy of 0.06 eV is obtained. For protium the activation energy is identical within the uncertainty limits.}, +@article{henriksson_difference_2005, + title = {Difference in formation of hydrogen and helium clusters in tungsten}, + volume = {87}, + issn = {0003-6951, 1077-3118}, + url = {http://aip.scitation.org/doi/10.1063/1.2103390}, + doi = {10.1063/1.2103390}, language = {en}, - urldate = {2022-03-15}, - journal = {Physica Scripta}, - author = {Holzner, G. and Schwarz-Selinger, T. and Dürbeck, T. and Toussaint, U. von}, - month = jan, - year = {2020}, - note = {Publisher: IOP Publishing}, - pages = {014034}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\Q8RAWZVY\\Holzner et al. - 2020 - Solute diffusion of hydrogen isotopes in tungsten—.pdf:application/pdf}, + number = {16}, + urldate = {2022-03-16}, + journal = {Applied Physics Letters}, + author = {Henriksson, K. O. E. and Nordlund, K. and Krasheninnikov, A. and Keinonen, J.}, + month = oct, + year = {2005}, + pages = {163113}, + file = {Henriksson et al. - 2005 - Difference in formation of hydrogen and helium clu.pdf:D\:\\Logiciels\\data_zotero\\storage\\MAN8CDTS\\Henriksson et al. - 2005 - Difference in formation of hydrogen and helium clu.pdf:application/pdf}, } -@article{zhou_molecular_2016, - title = {Molecular {Dynamics} {Simulations} of {Hydrogen} {Diffusion} in {Aluminum}}, - volume = {120}, - issn = {1932-7447, 1932-7455}, - url = {https://pubs.acs.org/doi/10.1021/acs.jpcc.6b01802}, - doi = {10.1021/acs.jpcc.6b01802}, - language = {en}, - number = {14}, - urldate = {2022-03-15}, - journal = {The Journal of Physical Chemistry C}, - author = {Zhou, X. W. and El Gabaly, F. and Stavila, V. and Allendorf, M. D.}, - month = apr, - year = {2016}, - pages = {7500--7509}, - file = {Zhou et al. - 2016 - Molecular Dynamics Simulations of Hydrogen Diffusi.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5XV8FV8H\\Zhou et al. - 2016 - Molecular Dynamics Simulations of Hydrogen Diffusi.pdf:application/pdf}, +@article{schmid_transport_2014, + title = {Transport of hydrogen in metals with occupancy dependent trap energies}, + volume = {116}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.4896580}, + doi = {10.1063/1.4896580}, + number = {13}, + urldate = {2022-03-28}, + journal = {Journal of Applied Physics}, + author = {Schmid, K. and von Toussaint, U. and Schwarz-Selinger, T.}, + month = oct, + year = {2014}, + note = {Publisher: American Institute of Physics}, + pages = {134901}, + file = {Version soumise:D\:\\Logiciels\\data_zotero\\storage\\2T6D2XD8\\Schmid et al. - 2014 - Transport of hydrogen in metals with occupancy dep.pdf:application/pdf}, } -@article{fu_trapping_2019, - title = {Trapping and detrapping process of hydrogen in tungsten divacancy: {A} molecular dynamics study}, - volume = {452}, - issn = {0168-583X}, - shorttitle = {Trapping and detrapping process of hydrogen in tungsten divacancy}, - url = {https://www.sciencedirect.com/science/article/pii/S0168583X19303714}, - doi = {10.1016/j.nimb.2019.05.050}, - abstract = {In future fusion devices, tungsten (W) and W-based alloys are the primary candidates for plasma facing materials, which experience high-energy neutron and high-flux hydrogen (H) isotopes and helium. Since mono-vacancy and di-vacancy are considered respectively as the common point defect and cluster under irradiation, the interaction between H and vacancies is concerned. In this work, the models to abstract the dynamical parameters, including the effective capture radii (ECRs) and dissociation coefficients, for various trapping and dissociation processes (VnHx + H ⇌ VnHx+1), were firstly extended based on molecular dynamics (MD) simulations. It was found that the ECRs and dissociation coefficients are dependent not only on the reaction types but also on the temperatures. As the increase of the trapped H atoms in the mono-/di-vacancy, the ECRs decrease gradually and the dissociation energies of H decrease gradually. It is not always valid that ECR is commonly assumed as one lattice constant or pre-exponential factor is commonly assumed as 10 ps−1. The number of trapped H in the vacancies should be related to the dwell time, and is also related to the temperature. These results should be potentially applicable for the long-term simulation methods such as kinetic Monte Carlo (KMC) and rate theory (RT) models.}, +@article{de_temmerman_nanostructuring_2012, + title = {Nanostructuring of molybdenum and tungsten surfaces by low-energy helium ions}, + volume = {30}, + issn = {0734-2101, 1520-8559}, + url = {http://avs.scitation.org/doi/10.1116/1.4731196}, + doi = {10.1116/1.4731196}, language = {en}, - urldate = {2022-03-15}, - journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, - author = {Fu, Baoqin and Qiu, Mingjie and Cui, Jiechao and Li, Min and Wang, Jun and Hou, Qing}, - month = aug, - year = {2019}, - keywords = {Hydrogen, Tungsten, Molecular dynamics, Detrapping, Vacancy}, - pages = {21--25}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4WEL5JCK\\S0168583X19303714.html:text/html}, + number = {4}, + urldate = {2022-03-18}, + journal = {Journal of Vacuum Science \& Technology A: Vacuum, Surfaces, and Films}, + author = {De Temmerman, Gregory and Bystrov, Kirill and Zielinski, Jakub J. and Balden, Martin and Matern, Gabriele and Arnas, Cecile and Marot, Laurent}, + month = jul, + year = {2012}, + pages = {041306}, + file = {De Temmerman et al. - 2012 - Nanostructuring of molybdenum and tungsten surface.pdf:D\:\\Logiciels\\data_zotero\\storage\\3P2WJ2MH\\De Temmerman et al. - 2012 - Nanostructuring of molybdenum and tungsten surface.pdf:application/pdf}, } @article{lam_modeling_2021, @@ -8343,41 +8543,121 @@ @article{lam_modeling_2021 month = jun, year = {2021}, pages = {24582--24592}, - file = {Lam et al. - 2021 - Modeling LiF and FLiBe Molten Salts with Robust Ne.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W8652XZZ\\Lam et al. - 2021 - Modeling LiF and FLiBe Molten Salts with Robust Ne.pdf:application/pdf}, + file = {Lam et al. - 2021 - Modeling LiF and FLiBe Molten Salts with Robust Ne.pdf:D\:\\Logiciels\\data_zotero\\storage\\W8652XZZ\\Lam et al. - 2021 - Modeling LiF and FLiBe Molten Salts with Robust Ne.pdf:application/pdf}, } -@article{de_temmerman_nanostructuring_2012, - title = {Nanostructuring of molybdenum and tungsten surfaces by low-energy helium ions}, - volume = {30}, - issn = {0734-2101, 1520-8559}, - url = {http://avs.scitation.org/doi/10.1116/1.4731196}, - doi = {10.1116/1.4731196}, +@article{behler_constructing_2015, + title = {Constructing high-dimensional neural network potentials: {A} tutorial review}, + volume = {115}, + issn = {00207608}, + shorttitle = {Constructing high-dimensional neural network potentials}, + url = {https://onlinelibrary.wiley.com/doi/10.1002/qua.24890}, + doi = {10.1002/qua.24890}, language = {en}, - number = {4}, + number = {16}, urldate = {2022-03-18}, - journal = {Journal of Vacuum Science \& Technology A: Vacuum, Surfaces, and Films}, - author = {De Temmerman, Gregory and Bystrov, Kirill and Zielinski, Jakub J. and Balden, Martin and Matern, Gabriele and Arnas, Cecile and Marot, Laurent}, - month = jul, - year = {2012}, - pages = {041306}, - file = {De Temmerman et al. - 2012 - Nanostructuring of molybdenum and tungsten surface.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3P2WJ2MH\\De Temmerman et al. - 2012 - Nanostructuring of molybdenum and tungsten surface.pdf:application/pdf}, + journal = {International Journal of Quantum Chemistry}, + author = {Behler, Jörg}, + month = aug, + year = {2015}, + pages = {1032--1050}, + file = {Behler - 2015 - Constructing high-dimensional neural network poten.pdf:D\:\\Logiciels\\data_zotero\\storage\\HDVEB9KR\\Behler - 2015 - Constructing high-dimensional neural network poten.pdf:application/pdf}, } -@article{schmid_transport_2014, - title = {Transport of hydrogen in metals with occupancy dependent trap energies}, - volume = {116}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.4896580}, - doi = {10.1063/1.4896580}, - number = {13}, - urldate = {2022-03-28}, - journal = {Journal of Applied Physics}, - author = {Schmid, K. and von Toussaint, U. and Schwarz-Selinger, T.}, +@article{romano_openmc_2015, + series = {Joint {International} {Conference} on {Supercomputing} in {Nuclear} {Applications} and {Monte} {Carlo} 2013, {SNA} + {MC} 2013. {Pluri}- and {Trans}-disciplinarity, {Towards} {New} {Modeling} and {Numerical} {Simulation} {Paradigms}}, + title = {{OpenMC}: {A} state-of-the-art {Monte} {Carlo} code for research and development}, + volume = {82}, + issn = {0306-4549}, + shorttitle = {{OpenMC}}, + url = {https://www.sciencedirect.com/science/article/pii/S030645491400379X}, + doi = {10.1016/j.anucene.2014.07.048}, + abstract = {This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology. OpenMC uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems. Modern, portable input/output file formats are used in OpenMC: XML for input, and HDF5 for output. High performance parallel algorithms in OpenMC have demonstrated near-linear scaling to over 100,000 processors on modern supercomputers. Other topics discussed in this paper include plotting, CMFD acceleration, variance reduction, eigenvalue calculations, and software development processes.}, + language = {en}, + urldate = {2022-03-31}, + journal = {Annals of Nuclear Energy}, + author = {Romano, Paul K. and Horelik, Nicholas E. and Herman, Bryan R. and Nelson, Adam G. and Forget, Benoit and Smith, Kord}, + month = aug, + year = {2015}, + keywords = {Parallel, Monte Carlo, HDF5, Neutron transport, OpenMC, XML}, + pages = {90--97}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7Z6DVQXL\\S030645491400379X.html:text/html}, +} + +@article{glugla_iter_2007, + series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, + title = {The {ITER} tritium systems}, + volume = {82}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379607000774}, + doi = {10.1016/j.fusengdes.2007.02.025}, + abstract = {ITER is the first fusion machine fully designed for operation with equimolar deuterium–tritium mixtures. The tokamak vessel will be fuelled through gas puffing and pellet injection, and the Neutral Beam heating system will introduce deuterium into the machine. Employing deuterium and tritium as fusion fuel will cause alpha heating of the plasma and will eventually provide energy. Due to the small burn-up fraction in the vacuum vessel a closed deuterium–tritium loop is required, along with all the auxiliary systems necessary for the safe handling of tritium. The ITER inner fuel cycle systems are designed to process considerable and unprecedented deuterium–tritium flow rates with high flexibility and reliability. High decontamination factors for effluent and release streams and low tritium inventories in all systems are needed to minimize chronic and accidental emissions. A multiple barrier concept assures the confinement of tritium within its respective processing components; atmosphere and vent detritiation systems are essential elements in this concept. Not only the interfaces between the primary fuel cycle systems – being procured through different Participant Teams – but also those to confinement systems such as Atmosphere Detritiation or those to fuelling and pumping – again procured through different Participant Teams – and interfaces to buildings are calling for definition and for detailed analysis to assure proper design integration. Considering the complexity of the ITER Tritium Plant configuration management and interface control will be a challenging task.}, + language = {en}, + number = {5}, + urldate = {2022-04-01}, + journal = {Fusion Engineering and Design}, + author = {Glugla, M. and Antipenkov, A. and Beloglazov, S. and Caldwell-Nichols, C. and Cristescu, I. R. and Cristescu, I. and Day, C. and Doerr, L. and Girard, J. -P. and Tada, E.}, month = oct, - year = {2014}, - note = {Publisher: American Institute of Physics}, - pages = {134901}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2T6D2XD8\\Schmid et al. - 2014 - Transport of hydrogen in metals with occupancy dep.pdf:application/pdf}, + year = {2007}, + keywords = {ITER, Confinement, Detritiation, Fuel cycle design, Tritium Plant, Vacuum pumping}, + pages = {472--487}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\NUDHFNB4\\S0920379607000774.html:text/html}, +} + +@article{ni_tritium_2013, + series = {Proceedings of the 27th {Symposium} {On} {Fusion} {Technology} ({SOFT}-27); {Liège}, {Belgium}, {September} 24-28, 2012}, + title = {Tritium supply assessment for {ITER} and {DEMOnstration} power plant}, + volume = {88}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379613004833}, + doi = {10.1016/j.fusengdes.2013.05.043}, + abstract = {The International Thermonuclear Experimental Reactor (ITER) and next generation DEMOnstration fusion reactor need amounts of tritium for test/initial startup and will consume kilograms tritium for operation per year. The available supply of tritium for fusion reactor is man-made sources. Now most of commercial tritium resource is extracted from moderator and coolant of CANada Deuterium Uranium (CANDU) type Heavy Water Reactor (HWR), in the Ontario Hydro Darlington facility of Canada and Wolsong facility of Korea. In this study, the tritium production rate in CANDU reactor was simulated and estimated. And other possible routes, including Accelerator Production of Tritium (APT), tritium production in Commercial Light Water Reactor (CLWR) and Accelerator Driven Subcritical system (ADS), were also evaluated in feasibility and economy. Based on the tritium requirement investigated according to ITER test schedule and startup inventory required for a FDS-II-scale DEMO calculated by TAS1.0, the assessment results showed that after ITER retired in 2038, the tritium inventory of CANDU reactor could not afford DEMO reactor startup without extra resource.}, + language = {en}, + number = {9}, + urldate = {2022-04-01}, + journal = {Fusion Engineering and Design}, + author = {Ni, Muyi and Wang, Yongliang and Yuan, Baoxin and Jiang, Jieqiong and Wu, Yican}, + month = oct, + year = {2013}, + keywords = {ITER, Fusion reactor, Heavy water reactor, Tritium supply}, + pages = {2422--2426}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\W4SGHLFP\\S0920379613004833.html:text/html}, +} + +@article{honda_analyses_2000, + title = {Analyses of loss of vacuum accident ({LOVA}) in {ITER}}, + volume = {47}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379699000678}, + doi = {10.1016/S0920-3796(99)00067-8}, + abstract = {A loss of vacuum accident (LOVA) is a unique event in fusion reactors. A reference event for ITER was postulated which was a failure of a penetration line (0.02 m2 cross-section) into a room with stack ventilation. Behavior of ingress air and environmental release of the inventory were calculated by an accident analysis code (MELCOR). No in-vessel component cooling was assumed because of a non-safety system and 1350 g-T as tritium (HTO) and 30 kg as tokamak dust (tungsten) were set in the vacuum vessel (VV) as the initial mobile inventory. Operation of the maintenance detritiation system (MDS) after 1 h was credited to limit the release. The analytical results showed that the environmental release of tritium (19 g-T) from the stack was a factor of 5 below the accidental release limit for ITER, and the release of dust (21 g) from the stack is a factor of 25 below the release limit. To investigate the ultimate safety margin, a hypothetical event was also analyzed which was a failure of a penetration line (0.2 m2 cross-section) into a room with ground level ventilation. Since the best estimate analysis assumed in-vessel cooling, which resulted in cooling down the walls, the mobile tritium inventory was reduced to 390 g-T. The large break size caused fast pressurization of the VV and thus the whole dust inventory (110 kg) was expected to be mobile. The ground level release was less than half of the no-evacuation limit under conservative weather conditions.}, + language = {en}, + number = {4}, + urldate = {2022-04-04}, + journal = {Fusion Engineering and Design}, + author = {Honda, T. and Bartels, H. -W. and Merrill, B. and Inabe, T. and Petti, D. and Moore, R. and Okazaki, T.}, + month = jan, + year = {2000}, + keywords = {Fusion reactors, Penetration line, Vacuum}, + pages = {361--375}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZQATI5TN\\S0920379699000678.html:text/html}, +} + +@article{friedlingstein_global_2021, + title = {Global {Carbon} {Budget} 2021}, + issn = {1866-3508}, + url = {https://essd.copernicus.org/preprints/essd-2021-386/}, + doi = {10.5194/essd-2021-386}, + abstract = {{\textless}p{\textgreater}{\textless}strong class="journal-contentHeaderColor"{\textgreater}Abstract.{\textless}/strong{\textgreater} Accurate assessment of anthropogenic carbon dioxide (CO$_{\textrm{2}}$) emissions and their redistribution among the atmosphere, ocean, and terrestrial biosphere in a changing climate is critical to better understand the global carbon cycle, support the development of climate policies, and project future climate change. Here we describe and synthesize data sets and methodology to quantify the five major components of the global carbon budget and their uncertainties. Fossil CO$_{\textrm{2}}$ emissions (E$_{\textrm{FOS}}$) are based on energy statistics and cement production data, while emissions from land-use change (E$_{\textrm{LUC}}$), mainly deforestation, are based on land-use and land-use change data and bookkeeping models. Atmospheric CO$_{\textrm{2}}$ concentration is measured directly, and its growth rate (G$_{\textrm{ATM}}$) is computed from the annual changes in concentration. The ocean CO$_{\textrm{2}}$ sink (S$_{\textrm{OCEAN}}$) is estimated with global ocean biogeochemistry models and observation-based data-products. The terrestrial CO$_{\textrm{2}}$ sink (S$_{\textrm{LAND}}$) is estimated with dynamic global vegetation models. The resulting carbon budget imbalance (B$_{\textrm{IM}}$), the difference between the estimated total emissions and the estimated changes in the atmosphere, ocean, and terrestrial biosphere, is a measure of imperfect data and understanding of the contemporary carbon cycle. All uncertainties are reported as \±1\σ. For the first time, an approach is shown to reconcile the difference in our E$_{\textrm{LUC}}$ estimate with the one from national greenhouse gases inventories, supporting the assessment of collective countries\’ climate progress.{\textless}/p{\textgreater} {\textless}p{\textgreater}For the year 2020, E$_{\textrm{FOS}}$ declined by 5.4\ \% relative to 2019, with fossil emissions at 9.5\ \±\ 0.5\ GtC\ yr$^{\textrm{\−1}}$ (9.3\ \±\ 0.5\ GtC\ yr$^{\textrm{\−1}}$ when the cement carbonation sink is included), E$_{\textrm{LUC}}$ was 0.9\ \±\ 0.7\ GtC\ yr$^{\textrm{\−1}}$, for a total anthropogenic CO$_{\textrm{2}}$ emission of 10.2\ \±\ 0.8\ GtC\ yr$^{\textrm{\−1}}$ (37.4\ \±\ 2.9\ GtCO$_{\textrm{2}}$). Also, for 2020, G$_{\textrm{ATM}}$ was 5.0\ \±\ 0.2\ GtC\ yr$^{\textrm{\−1}}$ (2.4\ \±\ 0.1\ ppm\ yr$^{\textrm{\−1}}$), S$_{\textrm{OCEAN}}$ was 3.0\ \±\ 0.4\ GtC\ yr$^{\textrm{\−1}}$ and S$_{\textrm{LAND}}$ was 2.9\ \±\ 1\ GtC\ yr$^{\textrm{\−1}}$, with a B$_{\textrm{IM}}$ of \−0.8\ GtC\ yr$^{\textrm{\−1}}$. The global atmospheric CO$_{\textrm{2}}$ concentration averaged over 2020 reached 412.45\ \±\ 0.1\ ppm. Preliminary data for 2021, suggest a rebound in E$_{\textrm{FOS}}$ relative to 2020 of +4.9\ \% (4.1\ \% to 5.7\ \%) globally.{\textless}/p{\textgreater} {\textless}p{\textgreater}Overall, the mean and trend in the components of the global carbon budget are consistently estimated over the period 1959\–2020, but discrepancies of up to 1\ GtC\ yr$^{\textrm{\−1}}$ persist for the representation of annual to semi-decadal variability in CO$_{\textrm{2}}$ fluxes. Comparison of estimates from multiple approaches and observations shows: (1) a persistent large uncertainty in the estimate of land-use changes emissions, (2) a low agreement between the different methods on the magnitude of the land CO$_{\textrm{2}}$ flux in the northern extra- tropics, and (3) a discrepancy between the different methods on the strength of the ocean sink over the last decade. This living data update documents changes in the methods and data sets used in this new global carbon budget and the progress in understanding of the global carbon cycle compared with previous publications of this data set (Friedlingstein et al., 2020; Friedlingstein et al., 2019; Le Qu\ér\é et al., 2018b, 2018a, 2016, 2015b, 2015a, 2014, 2013). The data presented in this work are available at {\textless}a href="https://doi.org/10.18160/gcp-2021" target="\_blank" rel="noopener"{\textgreater}https://doi.org/10.18160/gcp-2021{\textless}/a{\textgreater} (Friedlingstein et al., 2021).{\textless}/p{\textgreater}}, + language = {English}, + urldate = {2022-04-04}, + journal = {Earth System Science Data Discussions}, + author = {Friedlingstein, Pierre and Jones, Matthew W. and O'Sullivan, Michael and Andrew, Robbie M. and Bakker, Dorothee C. E. and Hauck, Judith and Le Quéré, Corinne and Peters, Glen P. and Peters, Wouter and Pongratz, Julia and Sitch, Stephen and Canadell, Josep G. and Ciais, Philippe and Jackson, Rob B. and Alin, Simone R. and Anthoni, Peter and Bates, Nicholas R. and Becker, Meike and Bellouin, Nicolas and Bopp, Laurent and Chau, Thi T. T. and Chevallier, Frédéric and Chini, Louise P. and Cronin, Margot and Currie, Kim I. and Decharme, Bertrand and Djeutchouang, Laique and Dou, Xinyu and Evans, Wiley and Feely, Richard A. and Feng, Liang and Gasser, Thomas and Gilfillan, Dennis and Gkritzalis, Thanos and Grassi, Giacomo and Gregor, Luke and Gruber, Nicolas and Gürses, Özgür and Harris, Ian and Houghton, Richard A. and Hurtt, George C. and Iida, Yosuke and Ilyina, Tatiana and Luijkx, Ingrid T. and Jain, Atul K. and Jones, Steve D. and Kato, Etsushi and Kennedy, Daniel and Klein Goldewijk, Kees and Knauer, Jürgen and Korsbakken, Jan Ivar and Körtzinger, Arne and Landschützer, Peter and Lauvset, Siv K. and Lefèvre, Nathalie and Lienert, Sebastian and Liu, Junjie and Marland, Gregg and McGuire, Patrick C. and Melton, Joe R. and Munro, David R. and Nabel, Julia E. M. S. and Nakaoka, Shin-Ichiro and Niwa, Yosuke and Ono, Tsuneo and Pierrot, Denis and Poulter, Benjamin and Rehder, Gregor and Resplandy, Laure and Robertson, Eddy and Rödenbeck, Christian and Rosan, Thais M. and Schwinger, Jörg and Schwingshackl, Clemens and Séférian, Roland and Sutton, Adrienne J. and Sweeney, Colm and Tanhua, Toste and Tans, Pieter P. and Tian, Hanqin and Tilbrook, Bronte and Tubiello, Francesco and van der Werf, Guido and Vuichard, Nicolas and Wada, Chisato and Wanninkhof, Rik and Watson, Andrew and Willis, David and Wiltshire, Andrew J. and Yuan, Wenping and Yue, Chao and Yue, Xu and Zaehle, Sönke and Zeng, Jiye}, + month = nov, + year = {2021}, + note = {Publisher: Copernicus GmbH}, + pages = {1--191}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FCKF9H74\\Friedlingstein et al. - 2021 - Global Carbon Budget 2021.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\456ZVRK7\\essd-2021-386.html:text/html}, } @techreport{humrickhouse_tritium_2020, @@ -8391,145 +8671,276 @@ @techreport{humrickhouse_tritium_2020 author = {Humrickhouse, Paul W. and Fuerst, Thomas F.}, month = sep, year = {2020}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GHQWJ4U2\\Humrickhouse et Fuerst - 2020 - Tritium Transport Phenomena in Molten-Salt Reactor.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MTLVPM5U\\1777267-tritium-transport-phenomena-molten-salt-reactors.html:text/html}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\GHQWJ4U2\\Humrickhouse et Fuerst - 2020 - Tritium Transport Phenomena in Molten-Salt Reactor.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MTLVPM5U\\1777267-tritium-transport-phenomena-molten-salt-reactors.html:text/html}, +} + +@article{dunand_surface_2022, + title = {Surface oxygen versus native oxide on tungsten: contrasting effects on deuterium retention and release}, + volume = {62}, + issn = {0029-5515}, + shorttitle = {Surface oxygen versus native oxide on tungsten}, + url = {https://doi.org/10.1088/1741-4326/ac583a}, + doi = {10.1088/1741-4326/ac583a}, + abstract = {We performed a direct comparison of deuterium retention and release from tungsten in presence or in absence of oxygen impurities. A single crystal of W(110) was used to prepare tungsten with four different surface states: with its native oxide, atomically clean, covered with half a monolayer of oxygen atoms, and covered with three fourths of a monolayer of oxygen atoms. For a D ion fluence of 3 × 1021 D+ m−2 implanted at 300 K, deuterium retention was highest with the native oxide, lowest with three fourths of a monolayer of oxygen atoms at the surface and intermediate for the clean surface. This counterintuitive result is explained by a different localization of deuterium retention in these samples. For tungsten with its native oxide, deuterium retention occurs solely in the bulk, i.e. below the first atomic plane of the surface. For clean tungsten, deuterium retention occurs in part at the surface and sputtering should play a role. For tungsten with a sub-monolayer surface coverage of oxygen atoms, a transition from surface to bulk retention is observed above half a monolayer of adsorbed oxygen. Striking differences in desorption peak(s) temperature(s) are observed between D ion-implanted samples and D2 molecules-exposed samples. These results highlight the importance of the (near-) surface localization of oxygen and deuterium on the temperature dependence of deuterium desorption rate i.e. on the fusion fuel recycling coefficient.}, + language = {en}, + number = {5}, + urldate = {2022-05-10}, + journal = {Nuclear Fusion}, + author = {Dunand, A. and Minissale, M. and Faure, J.-B. and Gallais, L. and Angot, T. and Bisson, R.}, + month = mar, + year = {2022}, + note = {Publisher: IOP Publishing}, + pages = {054002}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\QMKJVFFC\\Dunand et al. - 2022 - Surface oxygen versus native oxide on tungsten co.pdf:application/pdf}, +} + +@article{sawan_physics_2006, + series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, + title = {Physics and technology conditions for attaining tritium self-sufficiency for the {DT} fuel cycle}, + volume = {81}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379605006393}, + doi = {10.1016/j.fusengdes.2005.07.035}, + abstract = {There is no practical external source of tritium for fusion energy development beyond ITER and all subsequent fusion systems have to breed their own tritium. To ensure tritium self-sufficiency, the calculated achievable tritium breeding ratio (TBR) should be equal to or greater than the required TBR. The potential of achieving tritium self-sufficiency depends on many system physics and technology parameters. Interactive physics and technology R\&D programs should be implemented to determine the potential of realizing those physics and technology options and parameters that have large effects on attaining a realistic “window” for tritium self-sufficiency. The ranges of plasma and technology conditions that need to be met, in order to ensure tritium self-sufficiency, are identified.}, + language = {en}, + number = {8}, + urldate = {2022-05-09}, + journal = {Fusion Engineering and Design}, + author = {Sawan, M. E. and Abdou, M. A.}, + month = feb, + year = {2006}, + keywords = {Tritium self-sufficiency, Breeding blanket, Tritium inventory, DT fuel cycle, Tritium breeding ratio}, + pages = {1131--1144}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7399XK8L\\S0920379605006393.html:text/html}, +} + +@incollection{bockhoff_tritium_1983, + address = {Dordrecht}, + title = {Tritium {Breeding} in {Fusion} {Reactors}}, + isbn = {978-94-009-7101-1 978-94-009-7099-1}, + url = {http://link.springer.com/10.1007/978-94-009-7099-1_63}, + abstract = {Key technological problems that influence tritium breeding in fusion blankets are reviewed. The breeding potential of candidate materials is evaluated and compared to the tritium breeding requirements. The sensitivity of tritium breeding to design ard nuclear data parameters is reviewed. A framework for an integrated approach to improve tritium breeding prediction is discussed with emphasis on nuclear data requirements.}, + language = {en}, + urldate = {2022-05-09}, + booktitle = {Nuclear {Data} for {Science} and {Technology}}, + publisher = {Springer Netherlands}, + author = {Abdou, Mohamed A.}, + editor = {Böckhoff, K. H.}, + year = {1983}, + doi = {10.1007/978-94-009-7099-1_63}, + pages = {293--312}, + file = {Abdou - 1983 - Tritium Breeding in Fusion Reactors.pdf:D\:\\Logiciels\\data_zotero\\storage\\MQYJJT6M\\Abdou - 1983 - Tritium Breeding in Fusion Reactors.pdf:application/pdf}, } -@article{friedlingstein_global_2021, - title = {Global {Carbon} {Budget} 2021}, - issn = {1866-3508}, - url = {https://essd.copernicus.org/preprints/essd-2021-386/}, - doi = {10.5194/essd-2021-386}, - abstract = {{\textless}p{\textgreater}{\textless}strong class="journal-contentHeaderColor"{\textgreater}Abstract.{\textless}/strong{\textgreater} Accurate assessment of anthropogenic carbon dioxide (CO$_{\textrm{2}}$) emissions and their redistribution among the atmosphere, ocean, and terrestrial biosphere in a changing climate is critical to better understand the global carbon cycle, support the development of climate policies, and project future climate change. Here we describe and synthesize data sets and methodology to quantify the five major components of the global carbon budget and their uncertainties. Fossil CO$_{\textrm{2}}$ emissions (E$_{\textrm{FOS}}$) are based on energy statistics and cement production data, while emissions from land-use change (E$_{\textrm{LUC}}$), mainly deforestation, are based on land-use and land-use change data and bookkeeping models. Atmospheric CO$_{\textrm{2}}$ concentration is measured directly, and its growth rate (G$_{\textrm{ATM}}$) is computed from the annual changes in concentration. The ocean CO$_{\textrm{2}}$ sink (S$_{\textrm{OCEAN}}$) is estimated with global ocean biogeochemistry models and observation-based data-products. The terrestrial CO$_{\textrm{2}}$ sink (S$_{\textrm{LAND}}$) is estimated with dynamic global vegetation models. The resulting carbon budget imbalance (B$_{\textrm{IM}}$), the difference between the estimated total emissions and the estimated changes in the atmosphere, ocean, and terrestrial biosphere, is a measure of imperfect data and understanding of the contemporary carbon cycle. All uncertainties are reported as \±1\σ. For the first time, an approach is shown to reconcile the difference in our E$_{\textrm{LUC}}$ estimate with the one from national greenhouse gases inventories, supporting the assessment of collective countries\’ climate progress.{\textless}/p{\textgreater} {\textless}p{\textgreater}For the year 2020, E$_{\textrm{FOS}}$ declined by 5.4\ \% relative to 2019, with fossil emissions at 9.5\ \±\ 0.5\ GtC\ yr$^{\textrm{\−1}}$ (9.3\ \±\ 0.5\ GtC\ yr$^{\textrm{\−1}}$ when the cement carbonation sink is included), E$_{\textrm{LUC}}$ was 0.9\ \±\ 0.7\ GtC\ yr$^{\textrm{\−1}}$, for a total anthropogenic CO$_{\textrm{2}}$ emission of 10.2\ \±\ 0.8\ GtC\ yr$^{\textrm{\−1}}$ (37.4\ \±\ 2.9\ GtCO$_{\textrm{2}}$). Also, for 2020, G$_{\textrm{ATM}}$ was 5.0\ \±\ 0.2\ GtC\ yr$^{\textrm{\−1}}$ (2.4\ \±\ 0.1\ ppm\ yr$^{\textrm{\−1}}$), S$_{\textrm{OCEAN}}$ was 3.0\ \±\ 0.4\ GtC\ yr$^{\textrm{\−1}}$ and S$_{\textrm{LAND}}$ was 2.9\ \±\ 1\ GtC\ yr$^{\textrm{\−1}}$, with a B$_{\textrm{IM}}$ of \−0.8\ GtC\ yr$^{\textrm{\−1}}$. The global atmospheric CO$_{\textrm{2}}$ concentration averaged over 2020 reached 412.45\ \±\ 0.1\ ppm. Preliminary data for 2021, suggest a rebound in E$_{\textrm{FOS}}$ relative to 2020 of +4.9\ \% (4.1\ \% to 5.7\ \%) globally.{\textless}/p{\textgreater} {\textless}p{\textgreater}Overall, the mean and trend in the components of the global carbon budget are consistently estimated over the period 1959\–2020, but discrepancies of up to 1\ GtC\ yr$^{\textrm{\−1}}$ persist for the representation of annual to semi-decadal variability in CO$_{\textrm{2}}$ fluxes. Comparison of estimates from multiple approaches and observations shows: (1) a persistent large uncertainty in the estimate of land-use changes emissions, (2) a low agreement between the different methods on the magnitude of the land CO$_{\textrm{2}}$ flux in the northern extra- tropics, and (3) a discrepancy between the different methods on the strength of the ocean sink over the last decade. This living data update documents changes in the methods and data sets used in this new global carbon budget and the progress in understanding of the global carbon cycle compared with previous publications of this data set (Friedlingstein et al., 2020; Friedlingstein et al., 2019; Le Qu\ér\é et al., 2018b, 2018a, 2016, 2015b, 2015a, 2014, 2013). The data presented in this work are available at {\textless}a href="https://doi.org/10.18160/gcp-2021" target="\_blank" rel="noopener"{\textgreater}https://doi.org/10.18160/gcp-2021{\textless}/a{\textgreater} (Friedlingstein et al., 2021).{\textless}/p{\textgreater}}, - language = {English}, - urldate = {2022-04-04}, - journal = {Earth System Science Data Discussions}, - author = {Friedlingstein, Pierre and Jones, Matthew W. and O'Sullivan, Michael and Andrew, Robbie M. and Bakker, Dorothee C. E. and Hauck, Judith and Le Quéré, Corinne and Peters, Glen P. and Peters, Wouter and Pongratz, Julia and Sitch, Stephen and Canadell, Josep G. and Ciais, Philippe and Jackson, Rob B. and Alin, Simone R. and Anthoni, Peter and Bates, Nicholas R. and Becker, Meike and Bellouin, Nicolas and Bopp, Laurent and Chau, Thi T. T. and Chevallier, Frédéric and Chini, Louise P. and Cronin, Margot and Currie, Kim I. and Decharme, Bertrand and Djeutchouang, Laique and Dou, Xinyu and Evans, Wiley and Feely, Richard A. and Feng, Liang and Gasser, Thomas and Gilfillan, Dennis and Gkritzalis, Thanos and Grassi, Giacomo and Gregor, Luke and Gruber, Nicolas and Gürses, Özgür and Harris, Ian and Houghton, Richard A. and Hurtt, George C. and Iida, Yosuke and Ilyina, Tatiana and Luijkx, Ingrid T. and Jain, Atul K. and Jones, Steve D. and Kato, Etsushi and Kennedy, Daniel and Klein Goldewijk, Kees and Knauer, Jürgen and Korsbakken, Jan Ivar and Körtzinger, Arne and Landschützer, Peter and Lauvset, Siv K. and Lefèvre, Nathalie and Lienert, Sebastian and Liu, Junjie and Marland, Gregg and McGuire, Patrick C. and Melton, Joe R. and Munro, David R. and Nabel, Julia E. M. S. and Nakaoka, Shin-Ichiro and Niwa, Yosuke and Ono, Tsuneo and Pierrot, Denis and Poulter, Benjamin and Rehder, Gregor and Resplandy, Laure and Robertson, Eddy and Rödenbeck, Christian and Rosan, Thais M. and Schwinger, Jörg and Schwingshackl, Clemens and Séférian, Roland and Sutton, Adrienne J. and Sweeney, Colm and Tanhua, Toste and Tans, Pieter P. and Tian, Hanqin and Tilbrook, Bronte and Tubiello, Francesco and van der Werf, Guido and Vuichard, Nicolas and Wada, Chisato and Wanninkhof, Rik and Watson, Andrew and Willis, David and Wiltshire, Andrew J. and Yuan, Wenping and Yue, Chao and Yue, Xu and Zaehle, Sönke and Zeng, Jiye}, +@article{palermo_neutronic_2015, + title = {Neutronic design studies of a conceptual {DCLL} fusion reactor for a {DEMO} and a commercial power plant}, + volume = {56}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/0029-5515/56/1/016001}, + doi = {10.1088/0029-5515/56/1/016001}, + abstract = {Neutronic analyses or, more widely, nuclear analyses have been performed for the development of a dual-coolant He/LiPb (DCLL) conceptual design reactor. A detailed three-dimensional (3D) model has been examined and optimized. The design is based on the plasma parameters and functional materials of the power plant conceptual studies (PPCS) model C. The initial radial-build for the detailed model has been determined according to the dimensions established in a previous work on an equivalent simplified homogenized reactor model. For optimization purposes, the initial specifications established over the simplified model have been refined on the detailed 3D design, modifying material and dimension of breeding blanket, shield and vacuum vessel in order to fulfil the priority requirements of a fusion reactor in terms of the fundamental neutronic responses. Tritium breeding ratio, energy multiplication factor, radiation limits in the TF coils, helium production and displacements per atom (dpa) have been calculated in order to demonstrate the functionality and viability of the reactor design in guaranteeing tritium self-sufficiency, power efficiency, plasma confinement, and re-weldability and structural integrity of the components. The paper describes the neutronic design improvements of the DCLL reactor, obtaining results for both DEMO and power plant operational scenarios.}, + language = {en}, + number = {1}, + urldate = {2022-05-09}, + journal = {Nuclear Fusion}, + author = {Palermo, I. and Veredas, G. and Gómez-Ros, J. M. and Sanz, J. and Ibarra, A.}, month = nov, - year = {2021}, - note = {Publisher: Copernicus GmbH}, - pages = {1--191}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\456ZVRK7\\essd-2021-386.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\FCKF9H74\\Friedlingstein et al. - 2021 - Global Carbon Budget 2021.pdf:application/pdf}, + year = {2015}, + note = {Publisher: IOP Publishing}, + pages = {016001}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MM2EADDB\\Palermo et al. - 2015 - Neutronic design studies of a conceptual DCLL fusi.pdf:application/pdf}, } -@article{honda_analyses_2000, - title = {Analyses of loss of vacuum accident ({LOVA}) in {ITER}}, - volume = {47}, +@article{jaboulay_nuclear_2017, + series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, + title = {Nuclear analysis of the {HCLL} blanket for the {European} {DEMO}}, + volume = {124}, issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379699000678}, - doi = {10.1016/S0920-3796(99)00067-8}, - abstract = {A loss of vacuum accident (LOVA) is a unique event in fusion reactors. A reference event for ITER was postulated which was a failure of a penetration line (0.02 m2 cross-section) into a room with stack ventilation. Behavior of ingress air and environmental release of the inventory were calculated by an accident analysis code (MELCOR). No in-vessel component cooling was assumed because of a non-safety system and 1350 g-T as tritium (HTO) and 30 kg as tokamak dust (tungsten) were set in the vacuum vessel (VV) as the initial mobile inventory. Operation of the maintenance detritiation system (MDS) after 1 h was credited to limit the release. The analytical results showed that the environmental release of tritium (19 g-T) from the stack was a factor of 5 below the accidental release limit for ITER, and the release of dust (21 g) from the stack is a factor of 25 below the release limit. To investigate the ultimate safety margin, a hypothetical event was also analyzed which was a failure of a penetration line (0.2 m2 cross-section) into a room with ground level ventilation. Since the best estimate analysis assumed in-vessel cooling, which resulted in cooling down the walls, the mobile tritium inventory was reduced to 390 g-T. The large break size caused fast pressurization of the VV and thus the whole dust inventory (110 kg) was expected to be mobile. The ground level release was less than half of the no-evacuation limit under conservative weather conditions.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379617300716}, + doi = {10.1016/j.fusengdes.2017.01.050}, + abstract = {This paper presents the nuclear analysis of the European DEMO baseline 2015 with HCLL blanket carried out with the TRIPOLI-4® Monte Carlo code and the JEFF-3.2 nuclear data library. The TRIPOLI-4® model was imported from CAD using the McCad tool. A procedure that generates the detailed 3D model describing all the HCLL blanket internal structures was developed. This procedure allows parametrization of the blanket internal structures such as the number of cooling plates, manifolds, etc. and the thickness of the stiffening grid for instance. Different design variants were studied to improve the tritium production. From this previous study a complete nuclear analysis was carried out on a promising design which is a compromise between tritium production and mechanical robustness. All criteria (TBR, nuclear heating in coils and displacement damage in vacuum vessel) are met using this new reference design.}, language = {en}, - number = {4}, - urldate = {2022-04-04}, + urldate = {2022-05-09}, journal = {Fusion Engineering and Design}, - author = {Honda, T. and Bartels, H. -W. and Merrill, B. and Inabe, T. and Petti, D. and Moore, R. and Okazaki, T.}, - month = jan, - year = {2000}, - keywords = {Fusion reactors, Penetration line, Vacuum}, - pages = {361--375}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZQATI5TN\\S0920379699000678.html:text/html}, + author = {Jaboulay, Jean-Charles and Aiello, Giacomo and Aubert, Julien and Morin, Alexandro and Troisne, Marc}, + month = nov, + year = {2017}, + keywords = {DEMO, Tritium breeding, Blanket, Neutronics, TRIPOLI-4, HCLL, Nuclear heating}, + pages = {896--900}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\44LYQ8YM\\S0920379617300716.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\8M444FQK\\Jaboulay et al. - 2017 - Nuclear analysis of the HCLL blanket for the Europ.pdf:application/pdf}, } -@article{ni_tritium_2013, - series = {Proceedings of the 27th {Symposium} {On} {Fusion} {Technology} ({SOFT}-27); {Liège}, {Belgium}, {September} 24-28, 2012}, - title = {Tritium supply assessment for {ITER} and {DEMOnstration} power plant}, - volume = {88}, +@article{pereslavtsev_neutronic_2017, + series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, + title = {Neutronic analyses for the optimization of the advanced {HCPB} breeder blanket design for {DEMO}}, + volume = {124}, issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379613004833}, - doi = {10.1016/j.fusengdes.2013.05.043}, - abstract = {The International Thermonuclear Experimental Reactor (ITER) and next generation DEMOnstration fusion reactor need amounts of tritium for test/initial startup and will consume kilograms tritium for operation per year. The available supply of tritium for fusion reactor is man-made sources. Now most of commercial tritium resource is extracted from moderator and coolant of CANada Deuterium Uranium (CANDU) type Heavy Water Reactor (HWR), in the Ontario Hydro Darlington facility of Canada and Wolsong facility of Korea. In this study, the tritium production rate in CANDU reactor was simulated and estimated. And other possible routes, including Accelerator Production of Tritium (APT), tritium production in Commercial Light Water Reactor (CLWR) and Accelerator Driven Subcritical system (ADS), were also evaluated in feasibility and economy. Based on the tritium requirement investigated according to ITER test schedule and startup inventory required for a FDS-II-scale DEMO calculated by TAS1.0, the assessment results showed that after ITER retired in 2038, the tritium inventory of CANDU reactor could not afford DEMO reactor startup without extra resource.}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379617300388}, + doi = {10.1016/j.fusengdes.2017.01.028}, + abstract = {This work gives an overview of the neutronic analyses to support and optimize the advanced HCPB blanket concept for DEMO. Full scale 3D Monte Carlo particle transport simulations were performed to this end with the MCNP5 code employing a very detailed HCPB DEMO torus sector model. The HCPB blanket was optimized to fulfil the design requirements on tritium breeding, thermal stress stability and shielding performance.}, language = {en}, - number = {9}, - urldate = {2022-04-01}, + urldate = {2022-05-09}, journal = {Fusion Engineering and Design}, - author = {Ni, Muyi and Wang, Yongliang and Yuan, Baoxin and Jiang, Jieqiong and Wu, Yican}, - month = oct, - year = {2013}, - keywords = {ITER, Fusion reactor, Heavy water reactor, Tritium supply}, - pages = {2422--2426}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W4SGHLFP\\S0920379613004833.html:text/html}, + author = {Pereslavtsev, Pavel and Fischer, Ulrich and Hernandez, Francisco and Lu, Lei}, + month = nov, + year = {2017}, + keywords = {Neutronics, Breeder blanket, HCPB DEMO}, + pages = {910--914}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PHBVDWSV\\S0920379617300388.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\6XZNUXRQ\\Pereslavtsev et al. - 2017 - Neutronic analyses for the optimization of the adv.pdf:application/pdf}, } -@article{glugla_iter_2007, - series = {Proceedings of the 24th {Symposium} on {Fusion} {Technology}}, - title = {The {ITER} tritium systems}, - volume = {82}, +@article{hernandez_new_2017, + series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, + title = {A new {HCPB} breeding blanket for the {EU} {DEMO}: {Evolution}, rationale and preliminary performances}, + volume = {124}, issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379607000774}, - doi = {10.1016/j.fusengdes.2007.02.025}, - abstract = {ITER is the first fusion machine fully designed for operation with equimolar deuterium–tritium mixtures. The tokamak vessel will be fuelled through gas puffing and pellet injection, and the Neutral Beam heating system will introduce deuterium into the machine. Employing deuterium and tritium as fusion fuel will cause alpha heating of the plasma and will eventually provide energy. Due to the small burn-up fraction in the vacuum vessel a closed deuterium–tritium loop is required, along with all the auxiliary systems necessary for the safe handling of tritium. The ITER inner fuel cycle systems are designed to process considerable and unprecedented deuterium–tritium flow rates with high flexibility and reliability. High decontamination factors for effluent and release streams and low tritium inventories in all systems are needed to minimize chronic and accidental emissions. A multiple barrier concept assures the confinement of tritium within its respective processing components; atmosphere and vent detritiation systems are essential elements in this concept. Not only the interfaces between the primary fuel cycle systems – being procured through different Participant Teams – but also those to confinement systems such as Atmosphere Detritiation or those to fuelling and pumping – again procured through different Participant Teams – and interfaces to buildings are calling for definition and for detailed analysis to assure proper design integration. Considering the complexity of the ITER Tritium Plant configuration management and interface control will be a challenging task.}, + shorttitle = {A new {HCPB} breeding blanket for the {EU} {DEMO}}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379617300911}, + doi = {10.1016/j.fusengdes.2017.02.008}, + abstract = {The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in DEMO. During 2014 the former “beer-box” BB concept based on the ITER’s HCPB Test Blanket Module suffered several design changes so as to meet the different counteracting nuclear, thermohydraulic and thermomechanical requirements. These studies evidenced that the concept is too rigid to meet the tight TBR requirements imposed for the EU DEMO (i.e. TBR≥1.10). Additionally, the complex manifold system with unbalanced helium mass flow in each of the 2 parallel cooling loops made the concept thermohydraulically complex. However, parametric studies during 2015 revealed that the HCPB concept have potential for a better nuclear performance, as well as margin for a significant simplification of the cooling internals by redefining the cooling plates and the architecture of the blanket, building a symmetric flow scheme. This paper describes the new HCPB concept based on an integrated FW with the breeding zone thermohydraulics and helium manifold systems. The former complex manifold backplates have been compacted and integrated in the cooling plates, releasing ≈300mm of radial space that can be used now to increase breeder zone, the neutron shielding, to reinforce the Back Supporting Structure (BSS) or basically to reduce the reactor size. Detailed neutronic analyses have yielded a TBR of ∼1.20 for the baseline design. Initial analyses show a correct thermohydraulic behavior. Preliminary thermomechanical analyses also indicate that the design can potentially withstand an in-box LOCA at 9 MPa at a level C according to the RCC-MRx code. Future consolidation activities are described, which shall lead to a concept meeting the BB requirements.}, language = {en}, - number = {5}, - urldate = {2022-04-01}, + urldate = {2022-05-09}, journal = {Fusion Engineering and Design}, - author = {Glugla, M. and Antipenkov, A. and Beloglazov, S. and Caldwell-Nichols, C. and Cristescu, I. R. and Cristescu, I. and Day, C. and Doerr, L. and Girard, J. -P. and Tada, E.}, - month = oct, - year = {2007}, - keywords = {ITER, Confinement, Detritiation, Fuel cycle design, Tritium Plant, Vacuum pumping}, - pages = {472--487}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\NUDHFNB4\\S0920379607000774.html:text/html}, + author = {Hernández, F. and Pereslavtsev, P. and Kang, Q. and Norajitra, P. and Kiss, B. and Nádasi, G. and Bitz, O.}, + month = nov, + year = {2017}, + keywords = {DEMO, Breeding blanket, HCPB, TBR}, + pages = {882--886}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4TT3VMZN\\S0920379617300911.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\RU6WC7RG\\Hernández et al. - 2017 - A new HCPB breeding blanket for the EU DEMO Evolu.pdf:application/pdf}, } -@article{romano_openmc_2015, - series = {Joint {International} {Conference} on {Supercomputing} in {Nuclear} {Applications} and {Monte} {Carlo} 2013, {SNA} + {MC} 2013. {Pluri}- and {Trans}-disciplinarity, {Towards} {New} {Modeling} and {Numerical} {Simulation} {Paradigms}}, - title = {{OpenMC}: {A} state-of-the-art {Monte} {Carlo} code for research and development}, - volume = {82}, - issn = {0306-4549}, - shorttitle = {{OpenMC}}, - url = {https://www.sciencedirect.com/science/article/pii/S030645491400379X}, - doi = {10.1016/j.anucene.2014.07.048}, - abstract = {This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology. OpenMC uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems. Modern, portable input/output file formats are used in OpenMC: XML for input, and HDF5 for output. High performance parallel algorithms in OpenMC have demonstrated near-linear scaling to over 100,000 processors on modern supercomputers. Other topics discussed in this paper include plotting, CMFD acceleration, variance reduction, eigenvalue calculations, and software development processes.}, +@article{hernandez_overview_2018, + title = {Overview of the {HCPB} {Research} {Activities} in {EUROfusion}}, + volume = {46}, + issn = {1939-9375}, + doi = {10.1109/TPS.2018.2830813}, + abstract = {In the framework of the EUROfusion's Power Plant Physics and Technology, the working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One of these concepts is the helium-cooled pebble bed (HCPB) BB, which is based on the use of pebble beds of lithiated ternary compounds and Be or beryllides as tritium breeder and multiplier materials, respectively, EUROFER97 as structural steel and He as coolant. This paper aims at giving an overview of the EU HCPB BB Research and Development (R\&D) being developed at KIT, in collaboration with Wigner-RCP, BUTE-INT, and CIEMAT. The paper gives an outline of the HCPB BB design evolution, state-of-the-art basic functionalities, requirements and performances, and the associated R\&D activities in the areas of design, functional materials, manufacturing, and testing. In addition, attention is given also to the activities dedicated to the development of heat transfer augmentation techniques for the first wall and the corresponding testing. Due to their nature as design drivers, a brief overview in the R\&D of key HCPB interfacing areas is given as well, namely, the tritium extraction and recovery system, the primary heat transfer and power conversion systems, and safety topics, as well as some specific activities regarding the integration of in-vessel systems through the BB. As concluding remarks, an outline of the standing challenges and future R\&D plans is summarized.}, + number = {6}, + journal = {IEEE Transactions on Plasma Science}, + author = {Hernández, Francisco A. and Arbeiter, Frederik and Boccaccini, Lorenzo V. and Bubelis, Evaldas and Chakin, Vladimir P. and Cristescu, Ion and Ghidersa, Bradut E. and González, María and Hering, Wolfgang and Hernández, Teresa and Jin, Xue Z. and Kamlah, Marc and Kiss, Béla and Knitter, Regina and Kolb, Matthias. H. H. and Kurinskiy, Petr and Leys, Oliver and Maione, Ivan A. and Moscardini, Marigrazia and Nádasi, Gábor and Neuberger, Heiko and Pereslavtsev, Pavel and Pupeschi, Simone and Rolli, Rolf and Ruck, Sebastian and Spagnuolo, Gandolfo A. and Vladimirov, Pavel V. and Zeile, Christian and Zhou, Guangming}, + month = jun, + year = {2018}, + note = {Conference Name: IEEE Transactions on Plasma Science}, + keywords = {Heat transfer, EUROfusion, Safety, Collaboration, Coolants, demonstration fusion reactor (DEMO), Helium-cooled pebble bed (HCPB), Power generation, Steel, Tokamak devices, tritium breeding}, + pages = {2247--2261}, + file = {IEEE Xplore Abstract Record:D\:\\Logiciels\\data_zotero\\storage\\JARMTUHY\\8356249.html:text/html}, +} + +@article{shimada_blister_2003, + series = {Plasma-{Surface} {Interactions} in {Controlled} {Fusion} {Devices} 15}, + title = {Blister formation in tungsten by hydrogen and carbon mixed ion beam irradiation}, + volume = {313-316}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311502014472}, + doi = {10.1016/S0022-3115(02)01447-2}, + abstract = {Blister formation in tungsten has been studied by mixed carbon and hydrogen ion beam irradiation. The beam ion energies were 1.0 keV and 300 eV, and the fluence was in the range of 1024–1025 ionsm−2. It was found that a little amount of carbon impurity in the beam affected blister formation. A large number of blisters with various sizes were observed on the surface of tungsten at 653 K when the carbon concentration was more than 0.35\%. When the carbon concentration was 0.11\%, no blisters larger than 1.0 μm were observed. When the carbon concentration was 2.35\%, a carbon layer developed on the tungsten surface, and again, no blisters were observed. The effect of target temperature on blister formation was also investigated: the sizes and numbers of the blisters were the largest when the tungsten was irradiated at 653 K; when the sample was irradiated at 388 or 873 K, no blisters larger than 1.0 μm were observed.}, language = {en}, - urldate = {2022-03-31}, - journal = {Annals of Nuclear Energy}, - author = {Romano, Paul K. and Horelik, Nicholas E. and Herman, Bryan R. and Nelson, Adam G. and Forget, Benoit and Smith, Kord}, + urldate = {2022-05-09}, + journal = {Journal of Nuclear Materials}, + author = {Shimada, T. and Kikuchi, H. and Ueda, Y. and Sagara, A. and Nishikawa, M.}, + month = mar, + year = {2003}, + keywords = {Tungsten, Blistering, Carbon impurity, Mixed ion beam irradiation, PFM}, + pages = {204--208}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7V7E87AT\\S0022311502014472.html:text/html}, +} + +@article{wang_blister_2001, + title = {Blister formation of tungsten due to ion bombardment}, + volume = {299}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311501006791}, + doi = {10.1016/S0022-3115(01)00679-1}, + abstract = {Blisters formed at tungsten surfaces due to deuterium ion bombardment have been studied systematically in the energy range 100 eV to 1 keV. The bombardment with 1 keV D+ at room temperature (RT) shows that the blister size increases and the number decreases with the deuterium fluence from 1×1019 to 1×1021D+/cm2. No blisters are found at elevated temperatures between 600 and 800 °C. For bombardment with an energy as low as 100 eV, blisters are observed at the high fluence of 1×1021D+/cm2. The blister size increases and the number decreases with the bombardment energy. Combined with scanning electron microscopy (SEM) ion beam depth profiling measurements have been used to investigate the effect of blister formation on the trapping behavior of deuterium in tungsten. Double implantations, where 4 keV He+ and 100 eV D+, respectively, were injected in W prior to the bombardment of 1 keV D+ show a pronounced increase of deuterium retention and blister disappearance. Possible mechanisms are proposed to describe the observed phenomena.}, + language = {en}, + number = {2}, + urldate = {2022-05-09}, + journal = {Journal of Nuclear Materials}, + author = {Wang, Wenmin and Roth, J and Lindig, S and Wu, C. H}, + month = nov, + year = {2001}, + pages = {124--131}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SABJQU3I\\S0022311501006791.html:text/html}, +} + +@article{chen_irradiation_2019, + title = {Irradiation hardening induced by blistering in tungsten due to low-energy high flux hydrogen plasma exposure}, + volume = {522}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311518315484}, + doi = {10.1016/j.jnucmat.2019.05.004}, + abstract = {In this work, the microstructure evolution in the near-surface of tungsten under hydrogen (H) plasma exposure conditions was observed by means of scanning electron microscopy (SEM), plasma focused ion beam (FIB) and transmission electron microscopy (TEM) techniques. Blisters, with existing dislocations distributed around obviously, were observed beneath the tungsten surface when the exposure temperature was 573 K, which was rarely reported in previous studies. However, H bombardment at 1273 K did not lead to the formation of blister-like microstructures. Correspondingly, irradiation hardening occurred after low temperature exposure, but not after high temperature exposure, according to the Berkovich nano-indentation experiments. In order to characterize the indentation size effect and irradiation hardening behavior of plasma-exposed materials, a mechanistic model was proposed for the hardness-depth relationship. A good agreement between the experimental indentation data and theoretical results revealed that plasma-induced dislocations play a dominant role in determining the increase of hardness for H plasma-exposed tungsten.}, + language = {en}, + urldate = {2022-05-09}, + journal = {Journal of Nuclear Materials}, + author = {Chen, W. Q. and Xiao, X. Z. and Pang, B. and Si, S. S. and Jia, Y. Z. and Xu, B. and Morgan, T. W. and Liu, W. and Chiu, Y. L.}, month = aug, - year = {2015}, - keywords = {Monte Carlo, Parallel, HDF5, Neutron transport, OpenMC, XML}, - pages = {90--97}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7Z6DVQXL\\S030645491400379X.html:text/html}, + year = {2019}, + keywords = {TEM, Blistering, Irradiation hardening, Nano-indentation, Theoretical model}, + pages = {11--18}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\94GCZRPU\\Chen et al. - 2019 - Irradiation hardening induced by blistering in tun.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SVQ6P2H7\\S0022311518315484.html:text/html}, } -@article{martinez_thermal_2021, - title = {Thermal gradient effect on helium and self-interstitial transport in tungsten}, - volume = {130}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/5.0071935}, - doi = {10.1063/5.0071935}, - number = {21}, - urldate = {2022-04-13}, - journal = {Journal of Applied Physics}, - author = {Martínez, Enrique and Mathew, Nithin and Perez, Danny and Blondel, Sophie and Dasgupta, Dwaipayan and Wirth, Brian D. and Maroudas, Dimitrios}, - month = dec, - year = {2021}, - note = {Publisher: American Institute of Physics}, - pages = {215904}, +@article{ueda_hydrogen_2005, + series = {{PSI}-16}, + title = {Hydrogen blister formation and cracking behavior for various tungsten materials}, + volume = {337-339}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311504008475}, + doi = {10.1016/j.jnucmat.2004.10.077}, + abstract = {In order to study hydrogen blistering and subsequent cracking behavior of pure W, K-doped W, and La2O3-doped W, 1keV H3+ (main ion components) ion beams were irradiated at 653K to fluences up to 1×1025H/m2. Two pre-irradiation heat treatments were done for stress relief (900°C) and recrystallization (1300°C for pure W and 1500°C for K-doped and La2O3-doped W). It was found that blister characteristics and cracking behavior strongly depended on microstructures and dopant materials. For W materials with layered microstructure, blister shapes were mostly spherical-like, while for W materials with recrystallized (or disordered) microstructures, blisters had complicated plateau-like shapes with many cracks. Addition of K or La2O3 dopants increased the number of blisters and exfoliations for both stress relieved and recrystallized W.}, + language = {en}, + urldate = {2022-05-09}, + journal = {Journal of Nuclear Materials}, + author = {Ueda, Y. and Funabiki, T. and Shimada, T. and Fukumoto, K. and Kurishita, H. and Nishikawa, M.}, + month = mar, + year = {2005}, + keywords = {Tungsten, Bubbles and blisters, Ion surface interaction}, + pages = {1010--1014}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EPLP2X5Z\\Ueda et al. - 2005 - Hydrogen blister formation and cracking behavior f.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4KQLFJBI\\S0022311504008475.html:text/html}, } -@article{charles_modeling_2022, - title = {Modeling hydrogen dragging by mobile dislocations in finite element simulations}, - volume = {47}, - issn = {0360-3199}, - url = {https://www.sciencedirect.com/science/article/pii/S036031992200711X}, - doi = {10.1016/j.ijhydene.2022.02.099}, - abstract = {Finite element simulation modeling permits to predict hydrogen concentration for various initial boundary-values problems, but the results depend on the underlying transport mechanisms accounted for. Trapping process is a key factor in the apparent hydrogen diffusion, and the case of mobile traps as dislocations needs modification of the hydrogen transport equation usually considered in the literature. An extension of this model is proposed where hydrogen dragging by mobile traps is modeled by reaction-diffusion equations, involving trapping and detrapping kinetic, and is applied for evolving trap density with plastic strain. The consequences of trapped hydrogen mobility on diffusive hydrogen repartition in a reference Small Scale Yielding configuration are focused on, especially in term of acceleration of hydrogen transport. The potentiality of the model is illustrated by the modeling of the trapped hydrogen breakaway from fast moving dislocations.}, +@article{zhang_formation_2018, + title = {Formation of bubbles and blisters in hydrogen ion implanted polycrystalline tungsten}, + volume = {173}, + issn = {1042-0150, 1029-4953}, + url = {https://www.tandfonline.com/doi/full/10.1080/10420150.2018.1531411}, + doi = {10.1080/10420150.2018.1531411}, + abstract = {Tungsten (W) has been regarded as one of the most promising plasma facing materials (PFMs) in fusion reactors. The formation of bubbles and blisters during hydrogen (H) irradiation will affect the properties of W. The dependence of implantation conditions, such as fluence and energy, is therefore of great interest. In this work, polycrystalline tungsten samples were separated into two groups for study. The thick samples were implanted by 18 keV H3+ ions to fluences of 1 × 1018, 1 × 1019 and 1 × 1020 H+/cm2, respectively. Another thick sample was also implanted by 80 keV H2+ ions to a fluence of 2 × 1017 H+/cm2 for comparison. Moreover, the thin samples were implanted by 18 keV H3+ ions to fluences of 9.38 × 1016, 1.88 × 1017 and 5.63 × 1017 H+/cm2, respectively. Focused ion beam (FIB) combined with scanning electron microscopy (SEM) and transmission electron microscopy (TEM) were used for micro-structure analysis, while time-of-flight ion mass spectrometry (ToF-SIMS) was used to characterize the H depth profile. It is indicated that bubbles and blisters could form successively with increasing H+ fluence. H bubbles are formed at a fluence of ∼ 5.63 × 1017 H+/cm2, and H blisters are formed at ∼ 1 × 1019 H+/cm2 for 18 keV H3+ implantation. On the other hand, 80 keV H2+ ions can create more trapping sites in a shallow projected range, and thus enhancing the blisters formation with a relatively lower fluence of 2 × 1017 H+/cm2. The crack-like microstructures beneath the blisters are also observed and prefer to form on the deep side of the implanted range.}, language = {en}, - number = {28}, - urldate = {2022-04-20}, - journal = {International Journal of Hydrogen Energy}, - author = {Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, - month = apr, - year = {2022}, - keywords = {Dislocations, Finite elements calculations, Hydrogen diffusion, Trapping}, - pages = {13746--13761}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VR957JZT\\S036031992200711X.html:text/html}, + number = {11-12}, + urldate = {2022-05-09}, + journal = {Radiation Effects and Defects in Solids}, + author = {Zhang, Jiandong and Zhao, Jiangtao and Jiang, Weilin and Guan, Xingcai and Peng, Haibo and Zhu, Zihua and Wang, Tieshan}, + month = dec, + year = {2018}, + pages = {1027--1036}, + file = {Zhang et al. - 2018 - Formation of bubbles and blisters in hydrogen ion .pdf:D\:\\Logiciels\\data_zotero\\storage\\ERFQXLKD\\Zhang et al. - 2018 - Formation of bubbles and blisters in hydrogen ion .pdf:application/pdf}, +} + +@article{gavish_segev_hydrogen_2019, + title = {Hydrogen blister formation in single crystal and polycrystalline tungsten irradiated by {MeV} protons}, + volume = {513}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/S002231151831239X}, + doi = {10.1016/j.jnucmat.2018.11.005}, + abstract = {Single and polycrystalline tungsten samples were irradiated with 2.2 MeV protons at Soreq Applied Research Accelerator Facility (SARAF). Hydrogen blisters were obtained for both single crystal and polycrystalline samples, elucidating the role of grain boundaries in blister formation. The effect of temperature and flux on the critical formation dose for blisters and on their dimensions was studied. It was found that for single crystals, the critical formation dose is one order of magnitude higher than for polycrystalline tungsten at high temperature irradiation conditions. Upon reducing the irradiation temperature to ambient, the critical dose for formation of blisters in single crystals was reduced by a factor of three while in polycrystalline tungsten there was no significant change with temperature, thus indicating the role of grain boundaries in blister formation. Larger blisters were obtained in single crystals than in polycrystalline tungsten at ambient temperature conditions, identifying the grain boundaries as a preferential additional hydrogen trap. The height to area ratio of the blisters is found to be strongly temperature dependent and only weakly dependent on irradiation flux for both single and polycrystalline samples.}, + language = {en}, + urldate = {2022-05-09}, + journal = {Journal of Nuclear Materials}, + author = {Gavish Segev, I. and Yahel, E. and Silverman, I. and Perry, A. and Weismann, L. and Makov, G.}, + month = jan, + year = {2019}, + keywords = {Hydrogen, Tungsten, Irradiation damage, MeV protons}, + pages = {209--220}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3GMVCKXF\\Gavish Segev et al. - 2019 - Hydrogen blister formation in single crystal and p.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5FCSTYWZ\\S002231151831239X.html:text/html}, } @misc{noauthor_hydrogen_nodate, title = {Hydrogen isotope diffusive transport parameters in pure polycrystalline tungsten - {ScienceDirect}}, url = {https://www.sciencedirect.com/science/article/pii/S002231150100486X}, urldate = {2022-05-05}, - file = {Hydrogen isotope diffusive transport parameters in pure polycrystalline tungsten - ScienceDirect:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QPXJGQCY\\S002231150100486X.html:text/html}, + file = {Hydrogen isotope diffusive transport parameters in pure polycrystalline tungsten - ScienceDirect:D\:\\Logiciels\\data_zotero\\storage\\QPXJGQCY\\S002231150100486X.html:text/html}, } @techreport{d_iter_2016, @@ -8552,7 +8963,7 @@ @article{noh_hydrogen-isotope_2016 month = may, year = {2016}, pages = {112--118}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9W78RIEQ\\S0022311516300319.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9W78RIEQ\\S0022311516300319.html:text/html}, } @article{visca_manufacturing_2018, @@ -8569,7 +8980,7 @@ @article{visca_manufacturing_2018 month = nov, year = {2018}, pages = {1593--1596}, - file = {Visca et al. - 2018 - Manufacturing and testing of ITER-like divertor pl.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\N2M4GZU5\\Visca et al. - 2018 - Manufacturing and testing of ITER-like divertor pl.pdf:application/pdf}, + file = {Visca et al. - 2018 - Manufacturing and testing of ITER-like divertor pl.pdf:D\:\\Logiciels\\data_zotero\\storage\\N2M4GZU5\\Visca et al. - 2018 - Manufacturing and testing of ITER-like divertor pl.pdf:application/pdf}, } @phdthesis{durif_modelisation_2019, @@ -8585,6 +8996,7 @@ @phdthesis{durif_modelisation_2019 month = dec, year = {2019}, keywords = {Tungsten, ITER, Constitutive relations, Durée de vie, Durée de vie (ingénierie), Elastic-viscoplastic, Recristallisation, Recrystallization, Tungstène, Viscoplasticité}, + annote = {Sous la direction de Jean-Michel Bergheau, Guillaume Kermouche et de Marianne Richou. Soutenue le 04-12-2019,à Lyon , dans le cadre de École doctorale Sciences Ingénierie Santé (Saint-Etienne) , en partenariat avec Laboratoire de tribologie et dynamique des systèmes (Écully, Rhône) (laboratoire) , École Centrale de Lyon (établissement opérateur d'inscription) et de Ecole nationale d'ingénieurs (Saint-Etienne) (établissement opérateur d'inscription) .}, } @article{pajuste_tritium_2021, @@ -8603,7 +9015,7 @@ @article{pajuste_tritium_2021 year = {2021}, note = {Publisher: IOP Publishing}, pages = {124050}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RSIU9RJB\\Pajuste et al. - 2021 - Tritium in plasma-facing components of JET with th.pdf:application/pdf}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\RSIU9RJB\\Pajuste et al. - 2021 - Tritium in plasma-facing components of JET with th.pdf:application/pdf}, } @article{sugiyama_measurement_2004, @@ -8621,7 +9033,7 @@ @article{sugiyama_measurement_2004 year = {2004}, note = {Publisher: IOP Publishing}, pages = {68}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9YHCHUBB\\Sugiyama et al. - 2004 - Measurement of Tritium Surface Distribution on TFT.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZXW7GILA\\Physica.Topical.html:text/html}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZXW7GILA\\Physica.Topical.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\9YHCHUBB\\Sugiyama et al. - 2004 - Measurement of Tritium Surface Distribution on TFT.pdf:application/pdf}, } @article{linke_challenges_2019, @@ -8639,7 +9051,7 @@ @article{linke_challenges_2019 month = sep, year = {2019}, pages = {056201}, - file = {Linke et al. - 2019 - Challenges for plasma-facing components in nuclear.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\N5W9SUTK\\Linke et al. - 2019 - Challenges for plasma-facing components in nuclear.pdf:application/pdf}, + file = {Linke et al. - 2019 - Challenges for plasma-facing components in nuclear.pdf:D\:\\Logiciels\\data_zotero\\storage\\N5W9SUTK\\Linke et al. - 2019 - Challenges for plasma-facing components in nuclear.pdf:application/pdf}, } @article{ryutov_snowflake_2015, @@ -8656,7 +9068,7 @@ @article{ryutov_snowflake_2015 month = nov, year = {2015}, pages = {110901}, - file = {Ryutov et Soukhanovskii - 2015 - The snowflake divertor.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I47YZX9Z\\Ryutov et Soukhanovskii - 2015 - The snowflake divertor.pdf:application/pdf}, + file = {Ryutov et Soukhanovskii - 2015 - The snowflake divertor.pdf:D\:\\Logiciels\\data_zotero\\storage\\I47YZX9Z\\Ryutov et Soukhanovskii - 2015 - The snowflake divertor.pdf:application/pdf}, } @misc{noauthor_snowflake_nodate, @@ -8680,7 +9092,7 @@ @article{rodriguez-fernandez_overview_2022 year = {2022}, note = {Publisher: IOP Publishing}, pages = {042003}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PQCWXZN7\\Rodriguez-Fernandez et al. - 2022 - Overview of the SPARC physics basis towards the ex.pdf:application/pdf;Rodriguez-Fernandez - 2022 - Overview of the SPARC physics basis towards the ex.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QK4ZYVQH\\Rodriguez-Fernandez - 2022 - Overview of the SPARC physics basis towards the ex.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QNIUXFJM\\ac1654.html:text/html}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PQCWXZN7\\Rodriguez-Fernandez et al. - 2022 - Overview of the SPARC physics basis towards the ex.pdf:application/pdf;Rodriguez-Fernandez - 2022 - Overview of the SPARC physics basis towards the ex.pdf:D\:\\Logiciels\\data_zotero\\storage\\QK4ZYVQH\\Rodriguez-Fernandez - 2022 - Overview of the SPARC physics basis towards the ex.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QNIUXFJM\\ac1654.html:text/html}, } @article{havlickova_effect_2015, @@ -8698,7 +9110,7 @@ @article{havlickova_effect_2015 month = aug, year = {2015}, pages = {1209--1213}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9FRPQVIL\\S0022311514007570.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\9FRPQVIL\\S0022311514007570.html:text/html}, } @article{shimada_tritium_2018, @@ -8714,9 +9126,9 @@ @article{shimada_tritium_2018 author = {Shimada, M. and Pawelko, R. J.}, month = apr, year = {2018}, - keywords = {Tritium, Hydrogen, Permeation, Blanket, Reduced activation ferritic/martensitic steel}, + keywords = {Hydrogen, Permeation, Tritium, Blanket, Reduced activation ferritic/martensitic steel}, pages = {134--139}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ZK9KBPN2\\S0920379618301340.html:text/html;ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2GMYKNEK\\Shimada et Pawelko - 2018 - Tritium permeability measurement in hydrogen-triti.pdf:application/pdf}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\2GMYKNEK\\Shimada et Pawelko - 2018 - Tritium permeability measurement in hydrogen-triti.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\ZK9KBPN2\\S0920379618301340.html:text/html}, } @article{liger_overview_2018, @@ -8727,7 +9139,7 @@ @article{liger_overview_2018 author = {Liger, Karine}, year = {2018}, pages = {5}, - file = {Liger - 2018 - Overview of the TRANSAT (TRANSversal Actions for T.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SXPSH48T\\Liger - 2018 - Overview of the TRANSAT (TRANSversal Actions for T.pdf:application/pdf}, + file = {Liger - 2018 - Overview of the TRANSAT (TRANSversal Actions for T.pdf:D\:\\Logiciels\\data_zotero\\storage\\SXPSH48T\\Liger - 2018 - Overview of the TRANSAT (TRANSversal Actions for T.pdf:application/pdf}, } @article{lefebvre_preliminary_2012, @@ -8747,7 +9159,7 @@ @article{lefebvre_preliminary_2012 year = {2012}, keywords = {Tritium, Detritiation, Housekeeping, Membrane reactor}, pages = {1040--1044}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SHJRHKEQ\\S0920379612001366.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SHJRHKEQ\\S0920379612001366.html:text/html}, } @techreport{hyatt_radioactive_2021, @@ -8761,7 +9173,7 @@ @techreport{hyatt_radioactive_2021 author = {Hyatt, Neil}, month = nov, year = {2021}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I3I6QDT2\\radioactive-wastes-from-fusion-energy-preliminary-position-paper.html:text/html}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\I3I6QDT2\\radioactive-wastes-from-fusion-energy-preliminary-position-paper.html:text/html}, } @book{bridges_review_2007, @@ -8771,7 +9183,7 @@ @book{bridges_review_2007 author = {Bridges, Bryn and Elliott, Alex and Hill, Mark and Lambert, Barry and Little, Mark and Waters, Raymond and Phipps, Alan and Stather, John and Walker, Hilary}, month = nov, year = {2007}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\9ZCB77RC\\Bridges et al. - 2007 - Review of risks from tritium, Subgroup on Tritium .pdf:application/pdf}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\9ZCB77RC\\Bridges et al. - 2007 - Review of risks from tritium, Subgroup on Tritium .pdf:application/pdf}, } @article{janssens_emerging_2007, @@ -8782,7 +9194,7 @@ @article{janssens_emerging_2007 month = nov, year = {2007}, pages = {100}, - file = {Janssens - EUROPEAN COMMISSION.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\WVREF8SW\\Janssens - EUROPEAN COMMISSION.pdf:application/pdf}, + file = {Janssens - EUROPEAN COMMISSION.pdf:D\:\\Logiciels\\data_zotero\\storage\\WVREF8SW\\Janssens - EUROPEAN COMMISSION.pdf:application/pdf}, } @article{ivanova_plasma-facing_2012, @@ -8795,7 +9207,7 @@ @article{ivanova_plasma-facing_2012 author = {Ivanova, Darya}, year = {2012}, note = {Publisher: KTH Royal Institute of Technology}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\X4XAQML7\\Ivanova - 2012 - Plasma-Facing Components in Tokamaks Material Mo.pdf:application/pdf;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\2ZWPCU5R\\record.html:text/html}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\X4XAQML7\\Ivanova - 2012 - Plasma-Facing Components in Tokamaks Material Mo.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\2ZWPCU5R\\record.html:text/html}, } @article{mccracken_review_1980, @@ -8812,7 +9224,7 @@ @article{mccracken_review_1980 month = oct, year = {1980}, pages = {3--16}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HQSLSZQW\\McCracken - 1980 - A review of the experimental evidence for arcing a.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\C76RXQG8\\0022311580902998.html:text/html}, + file = {ScienceDirect Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\HQSLSZQW\\McCracken - 1980 - A review of the experimental evidence for arcing a.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\C76RXQG8\\0022311580902998.html:text/html}, } @book{knoll_radiation_1989, @@ -8847,7 +9259,7 @@ @article{watanabe_status_2011 year = {2011}, note = {Publisher: The Korean Physical Society}, pages = {1040--1045}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\VY6YRHIV\\view.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PQXZL9FL\\Watanabe et al. - 2011 - Status of JENDL High Energy File.pdf:application/pdf}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\PQXZL9FL\\Watanabe et al. - 2011 - Status of JENDL High Energy File.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VY6YRHIV\\view.html:text/html}, } @article{johnson_hydrogen_2010, @@ -8866,7 +9278,7 @@ @article{johnson_hydrogen_2010 month = feb, year = {2010}, pages = {315--327}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3MUCZVIK\\Johnson et Carter - 2010 - Hydrogen in tungsten Absorption, diffusion, vacan.pdf:application/pdf}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3MUCZVIK\\Johnson et Carter - 2010 - Hydrogen in tungsten Absorption, diffusion, vacan.pdf:application/pdf}, } @article{nojima_theoretical_2007, @@ -8885,7 +9297,7 @@ @article{nojima_theoretical_2007 year = {2007}, keywords = {Tungsten, Hydrogen diffusion, Density functional calculations, Hydrogen adsorption, Surface, Work function}, pages = {3003--3011}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\37DM4VUD\\S003960280700550X.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\37DM4VUD\\S003960280700550X.html:text/html}, } @article{tamm_interaction_1970, @@ -8920,7 +9332,7 @@ @article{alnot_adsorption_1989 month = may, year = {1989}, pages = {29--46}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7HS2DTDB\\0039602889906973.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7HS2DTDB\\0039602889906973.html:text/html}, } @article{heinola_first-principles_2010, @@ -8937,7 +9349,7 @@ @article{heinola_first-principles_2010 year = {2010}, note = {Publisher: American Physical Society}, pages = {073409}, - file = {APS Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PGJH2W5F\\PhysRevB.81.html:text/html}, + file = {APS Snapshot:D\:\\Logiciels\\data_zotero\\storage\\PGJH2W5F\\PhysRevB.81.html:text/html}, } @article{pyper_excited_2017, @@ -8957,7 +9369,7 @@ @article{pyper_excited_2017 \_eprint: https://doi.org/10.1080/09500839.2017.1347724}, keywords = {ab initio, computer modelling, EELS, Electronic structure}, pages = {295--303}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4R9PDQV8\\09500839.2017.html:text/html;Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4QT7886G\\Pyper et al. - 2017 - Excited helium under high pressures in the bulk an.pdf:application/pdf}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\4R9PDQV8\\09500839.2017.html:text/html;Version soumise:D\:\\Logiciels\\data_zotero\\storage\\4QT7886G\\Pyper et al. - 2017 - Excited helium under high pressures in the bulk an.pdf:application/pdf}, } @phdthesis{ialovega_surface_2021, @@ -8972,7 +9384,8 @@ @phdthesis{ialovega_surface_2021 collaborator = {Angot, Thierry and Bernard, Elodie}, month = feb, year = {2021}, - keywords = {Fusion au plasma, Fusion nucléaire par confinement magnétique, Helium, Hélium, Hydrogen, Hydrogène, Oxide, Oxyde, Physique nucléaire, Réacteur expérimental thermonucléaire international, Retention, Rétention, Tungsten, Tungstène}, + keywords = {Hydrogen, Tungsten, Retention, Helium, Tungstène, Fusion au plasma, Fusion nucléaire par confinement magnétique, Hélium, Hydrogène, Oxide, Oxyde, Physique nucléaire, Réacteur expérimental thermonucléaire international, Rétention}, + annote = {Sous la direction de Thierry Angot et de Elodie Bernard. Soutenue le 23-02-2021,à Aix-Marseille , dans le cadre de Ecole Doctorale Physique et Sciences de la Matière (Marseille) , en partenariat avec Institut de Recherche sur la Fusion par confinement Magnétique (CEA Cadarache) (laboratoire) et de Physique des Intéractions Ioniques et Moléculaires (PIIM) (Marseille) (laboratoire) .}, } @misc{stephen-dixon_aurora-multiphysicsachlys_2021, @@ -8986,269 +9399,42 @@ @misc{stephen-dixon_aurora-multiphysicsachlys_2021 month = dec, year = {2021}, doi = {10.5281/zenodo.6412090}, - file = {Zenodo Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\K9R4W4H9\\6412090.html:text/html}, -} - -@article{gavish_segev_hydrogen_2019, - title = {Hydrogen blister formation in single crystal and polycrystalline tungsten irradiated by {MeV} protons}, - volume = {513}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S002231151831239X}, - doi = {10.1016/j.jnucmat.2018.11.005}, - abstract = {Single and polycrystalline tungsten samples were irradiated with 2.2 MeV protons at Soreq Applied Research Accelerator Facility (SARAF). Hydrogen blisters were obtained for both single crystal and polycrystalline samples, elucidating the role of grain boundaries in blister formation. The effect of temperature and flux on the critical formation dose for blisters and on their dimensions was studied. It was found that for single crystals, the critical formation dose is one order of magnitude higher than for polycrystalline tungsten at high temperature irradiation conditions. Upon reducing the irradiation temperature to ambient, the critical dose for formation of blisters in single crystals was reduced by a factor of three while in polycrystalline tungsten there was no significant change with temperature, thus indicating the role of grain boundaries in blister formation. Larger blisters were obtained in single crystals than in polycrystalline tungsten at ambient temperature conditions, identifying the grain boundaries as a preferential additional hydrogen trap. The height to area ratio of the blisters is found to be strongly temperature dependent and only weakly dependent on irradiation flux for both single and polycrystalline samples.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Journal of Nuclear Materials}, - author = {Gavish Segev, I. and Yahel, E. and Silverman, I. and Perry, A. and Weismann, L. and Makov, G.}, - month = jan, - year = {2019}, - keywords = {Hydrogen, Tungsten, Irradiation damage, MeV protons}, - pages = {209--220}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3GMVCKXF\\Gavish Segev et al. - 2019 - Hydrogen blister formation in single crystal and p.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5FCSTYWZ\\S002231151831239X.html:text/html}, -} - -@article{zhang_formation_2018, - title = {Formation of bubbles and blisters in hydrogen ion implanted polycrystalline tungsten}, - volume = {173}, - issn = {1042-0150, 1029-4953}, - url = {https://www.tandfonline.com/doi/full/10.1080/10420150.2018.1531411}, - doi = {10.1080/10420150.2018.1531411}, - abstract = {Tungsten (W) has been regarded as one of the most promising plasma facing materials (PFMs) in fusion reactors. The formation of bubbles and blisters during hydrogen (H) irradiation will affect the properties of W. The dependence of implantation conditions, such as fluence and energy, is therefore of great interest. In this work, polycrystalline tungsten samples were separated into two groups for study. The thick samples were implanted by 18 keV H3+ ions to fluences of 1 × 1018, 1 × 1019 and 1 × 1020 H+/cm2, respectively. Another thick sample was also implanted by 80 keV H2+ ions to a fluence of 2 × 1017 H+/cm2 for comparison. Moreover, the thin samples were implanted by 18 keV H3+ ions to fluences of 9.38 × 1016, 1.88 × 1017 and 5.63 × 1017 H+/cm2, respectively. Focused ion beam (FIB) combined with scanning electron microscopy (SEM) and transmission electron microscopy (TEM) were used for micro-structure analysis, while time-of-flight ion mass spectrometry (ToF-SIMS) was used to characterize the H depth profile. It is indicated that bubbles and blisters could form successively with increasing H+ fluence. H bubbles are formed at a fluence of ∼ 5.63 × 1017 H+/cm2, and H blisters are formed at ∼ 1 × 1019 H+/cm2 for 18 keV H3+ implantation. On the other hand, 80 keV H2+ ions can create more trapping sites in a shallow projected range, and thus enhancing the blisters formation with a relatively lower fluence of 2 × 1017 H+/cm2. The crack-like microstructures beneath the blisters are also observed and prefer to form on the deep side of the implanted range.}, - language = {en}, - number = {11-12}, - urldate = {2022-05-09}, - journal = {Radiation Effects and Defects in Solids}, - author = {Zhang, Jiandong and Zhao, Jiangtao and Jiang, Weilin and Guan, Xingcai and Peng, Haibo and Zhu, Zihua and Wang, Tieshan}, - month = dec, - year = {2018}, - pages = {1027--1036}, - file = {Zhang et al. - 2018 - Formation of bubbles and blisters in hydrogen ion .pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ERFQXLKD\\Zhang et al. - 2018 - Formation of bubbles and blisters in hydrogen ion .pdf:application/pdf}, -} - -@article{ueda_hydrogen_2005, - series = {{PSI}-16}, - title = {Hydrogen blister formation and cracking behavior for various tungsten materials}, - volume = {337-339}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311504008475}, - doi = {10.1016/j.jnucmat.2004.10.077}, - abstract = {In order to study hydrogen blistering and subsequent cracking behavior of pure W, K-doped W, and La2O3-doped W, 1keV H3+ (main ion components) ion beams were irradiated at 653K to fluences up to 1×1025H/m2. Two pre-irradiation heat treatments were done for stress relief (900°C) and recrystallization (1300°C for pure W and 1500°C for K-doped and La2O3-doped W). It was found that blister characteristics and cracking behavior strongly depended on microstructures and dopant materials. For W materials with layered microstructure, blister shapes were mostly spherical-like, while for W materials with recrystallized (or disordered) microstructures, blisters had complicated plateau-like shapes with many cracks. Addition of K or La2O3 dopants increased the number of blisters and exfoliations for both stress relieved and recrystallized W.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Journal of Nuclear Materials}, - author = {Ueda, Y. and Funabiki, T. and Shimada, T. and Fukumoto, K. and Kurishita, H. and Nishikawa, M.}, - month = mar, - year = {2005}, - keywords = {Tungsten, Bubbles and blisters, Ion surface interaction}, - pages = {1010--1014}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EPLP2X5Z\\Ueda et al. - 2005 - Hydrogen blister formation and cracking behavior f.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4KQLFJBI\\S0022311504008475.html:text/html}, -} - -@article{chen_irradiation_2019, - title = {Irradiation hardening induced by blistering in tungsten due to low-energy high flux hydrogen plasma exposure}, - volume = {522}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311518315484}, - doi = {10.1016/j.jnucmat.2019.05.004}, - abstract = {In this work, the microstructure evolution in the near-surface of tungsten under hydrogen (H) plasma exposure conditions was observed by means of scanning electron microscopy (SEM), plasma focused ion beam (FIB) and transmission electron microscopy (TEM) techniques. Blisters, with existing dislocations distributed around obviously, were observed beneath the tungsten surface when the exposure temperature was 573 K, which was rarely reported in previous studies. However, H bombardment at 1273 K did not lead to the formation of blister-like microstructures. Correspondingly, irradiation hardening occurred after low temperature exposure, but not after high temperature exposure, according to the Berkovich nano-indentation experiments. In order to characterize the indentation size effect and irradiation hardening behavior of plasma-exposed materials, a mechanistic model was proposed for the hardness-depth relationship. A good agreement between the experimental indentation data and theoretical results revealed that plasma-induced dislocations play a dominant role in determining the increase of hardness for H plasma-exposed tungsten.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Journal of Nuclear Materials}, - author = {Chen, W. Q. and Xiao, X. Z. and Pang, B. and Si, S. S. and Jia, Y. Z. and Xu, B. and Morgan, T. W. and Liu, W. and Chiu, Y. L.}, - month = aug, - year = {2019}, - keywords = {Blistering, TEM, Irradiation hardening, Nano-indentation, Theoretical model}, - pages = {11--18}, - file = {ScienceDirect Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\94GCZRPU\\Chen et al. - 2019 - Irradiation hardening induced by blistering in tun.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SVQ6P2H7\\S0022311518315484.html:text/html}, -} - -@article{wang_blister_2001, - title = {Blister formation of tungsten due to ion bombardment}, - volume = {299}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311501006791}, - doi = {10.1016/S0022-3115(01)00679-1}, - abstract = {Blisters formed at tungsten surfaces due to deuterium ion bombardment have been studied systematically in the energy range 100 eV to 1 keV. The bombardment with 1 keV D+ at room temperature (RT) shows that the blister size increases and the number decreases with the deuterium fluence from 1×1019 to 1×1021D+/cm2. No blisters are found at elevated temperatures between 600 and 800 °C. For bombardment with an energy as low as 100 eV, blisters are observed at the high fluence of 1×1021D+/cm2. The blister size increases and the number decreases with the bombardment energy. Combined with scanning electron microscopy (SEM) ion beam depth profiling measurements have been used to investigate the effect of blister formation on the trapping behavior of deuterium in tungsten. Double implantations, where 4 keV He+ and 100 eV D+, respectively, were injected in W prior to the bombardment of 1 keV D+ show a pronounced increase of deuterium retention and blister disappearance. Possible mechanisms are proposed to describe the observed phenomena.}, - language = {en}, - number = {2}, - urldate = {2022-05-09}, - journal = {Journal of Nuclear Materials}, - author = {Wang, Wenmin and Roth, J and Lindig, S and Wu, C. H}, - month = nov, - year = {2001}, - pages = {124--131}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SABJQU3I\\S0022311501006791.html:text/html}, -} - -@article{shimada_blister_2003, - series = {Plasma-{Surface} {Interactions} in {Controlled} {Fusion} {Devices} 15}, - title = {Blister formation in tungsten by hydrogen and carbon mixed ion beam irradiation}, - volume = {313-316}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311502014472}, - doi = {10.1016/S0022-3115(02)01447-2}, - abstract = {Blister formation in tungsten has been studied by mixed carbon and hydrogen ion beam irradiation. The beam ion energies were 1.0 keV and 300 eV, and the fluence was in the range of 1024–1025 ionsm−2. It was found that a little amount of carbon impurity in the beam affected blister formation. A large number of blisters with various sizes were observed on the surface of tungsten at 653 K when the carbon concentration was more than 0.35\%. When the carbon concentration was 0.11\%, no blisters larger than 1.0 μm were observed. When the carbon concentration was 2.35\%, a carbon layer developed on the tungsten surface, and again, no blisters were observed. The effect of target temperature on blister formation was also investigated: the sizes and numbers of the blisters were the largest when the tungsten was irradiated at 653 K; when the sample was irradiated at 388 or 873 K, no blisters larger than 1.0 μm were observed.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Journal of Nuclear Materials}, - author = {Shimada, T. and Kikuchi, H. and Ueda, Y. and Sagara, A. and Nishikawa, M.}, - month = mar, - year = {2003}, - keywords = {Blistering, Tungsten, Carbon impurity, Mixed ion beam irradiation, PFM}, - pages = {204--208}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7V7E87AT\\S0022311502014472.html:text/html}, -} - -@article{hernandez_overview_2018, - title = {Overview of the {HCPB} {Research} {Activities} in {EUROfusion}}, - volume = {46}, - issn = {1939-9375}, - doi = {10.1109/TPS.2018.2830813}, - abstract = {In the framework of the EUROfusion's Power Plant Physics and Technology, the working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One of these concepts is the helium-cooled pebble bed (HCPB) BB, which is based on the use of pebble beds of lithiated ternary compounds and Be or beryllides as tritium breeder and multiplier materials, respectively, EUROFER97 as structural steel and He as coolant. This paper aims at giving an overview of the EU HCPB BB Research and Development (R\&D) being developed at KIT, in collaboration with Wigner-RCP, BUTE-INT, and CIEMAT. The paper gives an outline of the HCPB BB design evolution, state-of-the-art basic functionalities, requirements and performances, and the associated R\&D activities in the areas of design, functional materials, manufacturing, and testing. In addition, attention is given also to the activities dedicated to the development of heat transfer augmentation techniques for the first wall and the corresponding testing. Due to their nature as design drivers, a brief overview in the R\&D of key HCPB interfacing areas is given as well, namely, the tritium extraction and recovery system, the primary heat transfer and power conversion systems, and safety topics, as well as some specific activities regarding the integration of in-vessel systems through the BB. As concluding remarks, an outline of the standing challenges and future R\&D plans is summarized.}, - number = {6}, - journal = {IEEE Transactions on Plasma Science}, - author = {Hernández, Francisco A. and Arbeiter, Frederik and Boccaccini, Lorenzo V. and Bubelis, Evaldas and Chakin, Vladimir P. and Cristescu, Ion and Ghidersa, Bradut E. and González, María and Hering, Wolfgang and Hernández, Teresa and Jin, Xue Z. and Kamlah, Marc and Kiss, Béla and Knitter, Regina and Kolb, Matthias. H. H. and Kurinskiy, Petr and Leys, Oliver and Maione, Ivan A. and Moscardini, Marigrazia and Nádasi, Gábor and Neuberger, Heiko and Pereslavtsev, Pavel and Pupeschi, Simone and Rolli, Rolf and Ruck, Sebastian and Spagnuolo, Gandolfo A. and Vladimirov, Pavel V. and Zeile, Christian and Zhou, Guangming}, - month = jun, - year = {2018}, - note = {Conference Name: IEEE Transactions on Plasma Science}, - keywords = {Safety, EUROfusion, Heat transfer, Collaboration, Coolants, demonstration fusion reactor (DEMO), Helium-cooled pebble bed (HCPB), Power generation, Steel, Tokamak devices, tritium breeding}, - pages = {2247--2261}, - file = {IEEE Xplore Abstract Record:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\JARMTUHY\\8356249.html:text/html}, -} - -@article{hernandez_new_2017, - series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, - title = {A new {HCPB} breeding blanket for the {EU} {DEMO}: {Evolution}, rationale and preliminary performances}, - volume = {124}, - issn = {0920-3796}, - shorttitle = {A new {HCPB} breeding blanket for the {EU} {DEMO}}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379617300911}, - doi = {10.1016/j.fusengdes.2017.02.008}, - abstract = {The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in DEMO. During 2014 the former “beer-box” BB concept based on the ITER’s HCPB Test Blanket Module suffered several design changes so as to meet the different counteracting nuclear, thermohydraulic and thermomechanical requirements. These studies evidenced that the concept is too rigid to meet the tight TBR requirements imposed for the EU DEMO (i.e. TBR≥1.10). Additionally, the complex manifold system with unbalanced helium mass flow in each of the 2 parallel cooling loops made the concept thermohydraulically complex. However, parametric studies during 2015 revealed that the HCPB concept have potential for a better nuclear performance, as well as margin for a significant simplification of the cooling internals by redefining the cooling plates and the architecture of the blanket, building a symmetric flow scheme. This paper describes the new HCPB concept based on an integrated FW with the breeding zone thermohydraulics and helium manifold systems. The former complex manifold backplates have been compacted and integrated in the cooling plates, releasing ≈300mm of radial space that can be used now to increase breeder zone, the neutron shielding, to reinforce the Back Supporting Structure (BSS) or basically to reduce the reactor size. Detailed neutronic analyses have yielded a TBR of ∼1.20 for the baseline design. Initial analyses show a correct thermohydraulic behavior. Preliminary thermomechanical analyses also indicate that the design can potentially withstand an in-box LOCA at 9 MPa at a level C according to the RCC-MRx code. Future consolidation activities are described, which shall lead to a concept meeting the BB requirements.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Fusion Engineering and Design}, - author = {Hernández, F. and Pereslavtsev, P. and Kang, Q. and Norajitra, P. and Kiss, B. and Nádasi, G. and Bitz, O.}, - month = nov, - year = {2017}, - keywords = {DEMO, Breeding blanket, HCPB, TBR}, - pages = {882--886}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\RU6WC7RG\\Hernández et al. - 2017 - A new HCPB breeding blanket for the EU DEMO Evolu.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4TT3VMZN\\S0920379617300911.html:text/html}, -} - -@article{pereslavtsev_neutronic_2017, - series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, - title = {Neutronic analyses for the optimization of the advanced {HCPB} breeder blanket design for {DEMO}}, - volume = {124}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379617300388}, - doi = {10.1016/j.fusengdes.2017.01.028}, - abstract = {This work gives an overview of the neutronic analyses to support and optimize the advanced HCPB blanket concept for DEMO. Full scale 3D Monte Carlo particle transport simulations were performed to this end with the MCNP5 code employing a very detailed HCPB DEMO torus sector model. The HCPB blanket was optimized to fulfil the design requirements on tritium breeding, thermal stress stability and shielding performance.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Fusion Engineering and Design}, - author = {Pereslavtsev, Pavel and Fischer, Ulrich and Hernandez, Francisco and Lu, Lei}, - month = nov, - year = {2017}, - keywords = {Neutronics, Breeder blanket, HCPB DEMO}, - pages = {910--914}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6XZNUXRQ\\Pereslavtsev et al. - 2017 - Neutronic analyses for the optimization of the adv.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\PHBVDWSV\\S0920379617300388.html:text/html}, -} - -@article{jaboulay_nuclear_2017, - series = {Proceedings of the 29th {Symposium} on {Fusion} {Technology} ({SOFT}-29) {Prague}, {Czech} {Republic}, {September} 5-9, 2016}, - title = {Nuclear analysis of the {HCLL} blanket for the {European} {DEMO}}, - volume = {124}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379617300716}, - doi = {10.1016/j.fusengdes.2017.01.050}, - abstract = {This paper presents the nuclear analysis of the European DEMO baseline 2015 with HCLL blanket carried out with the TRIPOLI-4® Monte Carlo code and the JEFF-3.2 nuclear data library. The TRIPOLI-4® model was imported from CAD using the McCad tool. A procedure that generates the detailed 3D model describing all the HCLL blanket internal structures was developed. This procedure allows parametrization of the blanket internal structures such as the number of cooling plates, manifolds, etc. and the thickness of the stiffening grid for instance. Different design variants were studied to improve the tritium production. From this previous study a complete nuclear analysis was carried out on a promising design which is a compromise between tritium production and mechanical robustness. All criteria (TBR, nuclear heating in coils and displacement damage in vacuum vessel) are met using this new reference design.}, - language = {en}, - urldate = {2022-05-09}, - journal = {Fusion Engineering and Design}, - author = {Jaboulay, Jean-Charles and Aiello, Giacomo and Aubert, Julien and Morin, Alexandro and Troisne, Marc}, - month = nov, - year = {2017}, - keywords = {DEMO, HCLL, Neutronics, Tritium breeding, TRIPOLI-4, Blanket, Nuclear heating}, - pages = {896--900}, - file = {Version soumise:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\8M444FQK\\Jaboulay et al. - 2017 - Nuclear analysis of the HCLL blanket for the Europ.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\44LYQ8YM\\S0920379617300716.html:text/html}, -} - -@article{palermo_neutronic_2015, - title = {Neutronic design studies of a conceptual {DCLL} fusion reactor for a {DEMO} and a commercial power plant}, - volume = {56}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/0029-5515/56/1/016001}, - doi = {10.1088/0029-5515/56/1/016001}, - abstract = {Neutronic analyses or, more widely, nuclear analyses have been performed for the development of a dual-coolant He/LiPb (DCLL) conceptual design reactor. A detailed three-dimensional (3D) model has been examined and optimized. The design is based on the plasma parameters and functional materials of the power plant conceptual studies (PPCS) model C. The initial radial-build for the detailed model has been determined according to the dimensions established in a previous work on an equivalent simplified homogenized reactor model. For optimization purposes, the initial specifications established over the simplified model have been refined on the detailed 3D design, modifying material and dimension of breeding blanket, shield and vacuum vessel in order to fulfil the priority requirements of a fusion reactor in terms of the fundamental neutronic responses. Tritium breeding ratio, energy multiplication factor, radiation limits in the TF coils, helium production and displacements per atom (dpa) have been calculated in order to demonstrate the functionality and viability of the reactor design in guaranteeing tritium self-sufficiency, power efficiency, plasma confinement, and re-weldability and structural integrity of the components. The paper describes the neutronic design improvements of the DCLL reactor, obtaining results for both DEMO and power plant operational scenarios.}, - language = {en}, - number = {1}, - urldate = {2022-05-09}, - journal = {Nuclear Fusion}, - author = {Palermo, I. and Veredas, G. and Gómez-Ros, J. M. and Sanz, J. and Ibarra, A.}, - month = nov, - year = {2015}, - note = {Publisher: IOP Publishing}, - pages = {016001}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MM2EADDB\\Palermo et al. - 2015 - Neutronic design studies of a conceptual DCLL fusi.pdf:application/pdf}, -} - -@incollection{bockhoff_tritium_1983, - address = {Dordrecht}, - title = {Tritium {Breeding} in {Fusion} {Reactors}}, - isbn = {978-94-009-7101-1 978-94-009-7099-1}, - url = {http://link.springer.com/10.1007/978-94-009-7099-1_63}, - abstract = {Key technological problems that influence tritium breeding in fusion blankets are reviewed. The breeding potential of candidate materials is evaluated and compared to the tritium breeding requirements. The sensitivity of tritium breeding to design ard nuclear data parameters is reviewed. A framework for an integrated approach to improve tritium breeding prediction is discussed with emphasis on nuclear data requirements.}, - language = {en}, - urldate = {2022-05-09}, - booktitle = {Nuclear {Data} for {Science} and {Technology}}, - publisher = {Springer Netherlands}, - author = {Abdou, Mohamed A.}, - editor = {Böckhoff, K. H.}, - year = {1983}, - doi = {10.1007/978-94-009-7099-1_63}, - pages = {293--312}, - file = {Abdou - 1983 - Tritium Breeding in Fusion Reactors.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MQYJJT6M\\Abdou - 1983 - Tritium Breeding in Fusion Reactors.pdf:application/pdf}, -} - -@article{sawan_physics_2006, - series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, - title = {Physics and technology conditions for attaining tritium self-sufficiency for the {DT} fuel cycle}, - volume = {81}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379605006393}, - doi = {10.1016/j.fusengdes.2005.07.035}, - abstract = {There is no practical external source of tritium for fusion energy development beyond ITER and all subsequent fusion systems have to breed their own tritium. To ensure tritium self-sufficiency, the calculated achievable tritium breeding ratio (TBR) should be equal to or greater than the required TBR. The potential of achieving tritium self-sufficiency depends on many system physics and technology parameters. Interactive physics and technology R\&D programs should be implemented to determine the potential of realizing those physics and technology options and parameters that have large effects on attaining a realistic “window” for tritium self-sufficiency. The ranges of plasma and technology conditions that need to be met, in order to ensure tritium self-sufficiency, are identified.}, - language = {en}, - number = {8}, - urldate = {2022-05-09}, - journal = {Fusion Engineering and Design}, - author = {Sawan, M. E. and Abdou, M. A.}, - month = feb, - year = {2006}, - keywords = {Breeding blanket, Tritium inventory, Tritium self-sufficiency, DT fuel cycle, Tritium breeding ratio}, - pages = {1131--1144}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7399XK8L\\S0920379605006393.html:text/html}, + file = {Zenodo Snapshot:D\:\\Logiciels\\data_zotero\\storage\\K9R4W4H9\\6412090.html:text/html}, } -@article{dunand_surface_2022, - title = {Surface oxygen versus native oxide on tungsten: contrasting effects on deuterium retention and release}, - volume = {62}, - issn = {0029-5515}, - shorttitle = {Surface oxygen versus native oxide on tungsten}, - url = {https://doi.org/10.1088/1741-4326/ac583a}, - doi = {10.1088/1741-4326/ac583a}, - abstract = {We performed a direct comparison of deuterium retention and release from tungsten in presence or in absence of oxygen impurities. A single crystal of W(110) was used to prepare tungsten with four different surface states: with its native oxide, atomically clean, covered with half a monolayer of oxygen atoms, and covered with three fourths of a monolayer of oxygen atoms. For a D ion fluence of 3 × 1021 D+ m−2 implanted at 300 K, deuterium retention was highest with the native oxide, lowest with three fourths of a monolayer of oxygen atoms at the surface and intermediate for the clean surface. This counterintuitive result is explained by a different localization of deuterium retention in these samples. For tungsten with its native oxide, deuterium retention occurs solely in the bulk, i.e. below the first atomic plane of the surface. For clean tungsten, deuterium retention occurs in part at the surface and sputtering should play a role. For tungsten with a sub-monolayer surface coverage of oxygen atoms, a transition from surface to bulk retention is observed above half a monolayer of adsorbed oxygen. Striking differences in desorption peak(s) temperature(s) are observed between D ion-implanted samples and D2 molecules-exposed samples. These results highlight the importance of the (near-) surface localization of oxygen and deuterium on the temperature dependence of deuterium desorption rate i.e. on the fusion fuel recycling coefficient.}, - language = {en}, - number = {5}, - urldate = {2022-05-10}, - journal = {Nuclear Fusion}, - author = {Dunand, A. and Minissale, M. and Faure, J.-B. and Gallais, L. and Angot, T. and Bisson, R.}, - month = mar, +@article{charles_modeling_2022, + title = {Modeling hydrogen dragging by mobile dislocations in finite element simulations}, + volume = {47}, + issn = {0360-3199}, + url = {https://www.sciencedirect.com/science/article/pii/S036031992200711X}, + doi = {10.1016/j.ijhydene.2022.02.099}, + abstract = {Finite element simulation modeling permits to predict hydrogen concentration for various initial boundary-values problems, but the results depend on the underlying transport mechanisms accounted for. Trapping process is a key factor in the apparent hydrogen diffusion, and the case of mobile traps as dislocations needs modification of the hydrogen transport equation usually considered in the literature. An extension of this model is proposed where hydrogen dragging by mobile traps is modeled by reaction-diffusion equations, involving trapping and detrapping kinetic, and is applied for evolving trap density with plastic strain. The consequences of trapped hydrogen mobility on diffusive hydrogen repartition in a reference Small Scale Yielding configuration are focused on, especially in term of acceleration of hydrogen transport. The potentiality of the model is illustrated by the modeling of the trapped hydrogen breakaway from fast moving dislocations.}, + language = {en}, + number = {28}, + urldate = {2022-04-20}, + journal = {International Journal of Hydrogen Energy}, + author = {Charles, Yann and Mougenot, Jonathan and Gaspérini, Monique}, + month = apr, year = {2022}, - note = {Publisher: IOP Publishing}, - pages = {054002}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QMKJVFFC\\Dunand et al. - 2022 - Surface oxygen versus native oxide on tungsten co.pdf:application/pdf}, + keywords = {Hydrogen diffusion, Trapping, Dislocations, Finite elements calculations}, + pages = {13746--13761}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\VR957JZT\\S036031992200711X.html:text/html}, +} + +@article{martinez_thermal_2021, + title = {Thermal gradient effect on helium and self-interstitial transport in tungsten}, + volume = {130}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/5.0071935}, + doi = {10.1063/5.0071935}, + number = {21}, + urldate = {2022-04-13}, + journal = {Journal of Applied Physics}, + author = {Martínez, Enrique and Mathew, Nithin and Perez, Danny and Blondel, Sophie and Dasgupta, Dwaipayan and Wirth, Brian D. and Maroudas, Dimitrios}, + month = dec, + year = {2021}, + note = {Publisher: American Institute of Physics}, + pages = {215904}, } @article{bouhattate_computational_2011, @@ -9266,46 +9452,28 @@ @article{bouhattate_computational_2011 author = {Bouhattate, J. and Legrand, E. and Feaugas, X.}, month = sep, year = {2011}, - keywords = {Hydrogen, Diffusion, Trapping, Permeation, Modelling}, + keywords = {Hydrogen, Diffusion, Permeation, Trapping, Modelling}, pages = {12644--12652}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YDIXWYH3\\S0360319911016156.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\YDIXWYH3\\S0360319911016156.html:text/html}, } -@article{yan_numerical_2020, - title = {Numerical {Calculation} on {Recycling} {Ratio} of {Tritium} from {Tungsten} {Wall} {Used} in {Current} {CFETR} {Design}}, - volume = {39}, - issn = {1572-9591}, - url = {https://doi.org/10.1007/s10894-020-00247-4}, - doi = {10.1007/s10894-020-00247-4}, - abstract = {The recycling of tritium from plasma facing wall is an important neutral fuel source (in atomic and molecular form) for plasma confinement and particle control. In this study, the recycling process at tungsten wall based on current CFETR design was modeled. Monte Carlo code SRIM was used to model the implantation of energetic tritium ions into pure tungsten and to get back-scattering fraction of ions and the distribution of implanted tritium ions. The diffusion process of atoms in materials, with recombination at surface as boundary condition, was simulated using numerical approach for both stead and transient state. The total recycling ratio was contributed by fast process (implantation and back scattering) and slow process (diffusion and recombination) and its value nearly equals to 1 for stead state. Temporal dependence of total recycling ratio mainly depended on the slow process and was limited by diffusion coefficient in the bulk near surface and existence of traps in material. For tungsten material with good surface condition, the time of 90\% recycling was characterized as 1 ms and affected by temperature, recombination coefficient and concentration of traps while the thickness of material had less affection. Isotope effect that recycling ratio of tritium was larger than that of deuterium at the same situation was also found in the simulation and this effect may affect particle balance and fueling in D-T plasma operation. A collection of theoretical models to estimate the recycling ratio and its time dependence were also summarized and validated by the simulation results.}, +@book{logg_automated_2012, + edition = {1}, + title = {Automated {Solution} of {Differential} {Equations} by the {Finite} {Element} {Method}}, + isbn = {978-3-662-50833-6}, + url = {https://link.springer.com/book/10.1007/978-3-642-23099-8}, language = {en}, - number = {4}, - urldate = {2022-05-13}, - journal = {Journal of Fusion Energy}, - author = {Yan, Qiang and Chen, Zhongwen and Wang, Zhijun and Kong, Defeng and Wang, Xiang and Gou, Fujun and Zhang, Kun}, - month = aug, - year = {2020}, - keywords = {Tungsten, Fusion energy, Plasma material interaction, Wall tritium recycling}, - pages = {163--177}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SG2NE6NS\\Yan et al. - 2020 - Numerical Calculation on Recycling Ratio of Tritiu.pdf:application/pdf}, + urldate = {2022-05-17}, + author = {Logg, Anders and Mardal, Kent-Andre and Wells, Garth}, + year = {2012}, + file = {Snapshot:D\:\\Logiciels\\data_zotero\\storage\\H9C7NS6T\\978-3-642-23099-8.html:text/html}, } -@article{shimada_improved_2019, - title = {Improved tritium retention modeling with reaction-diffusion code {TMAP} and bulk depth profiling capability}, - volume = {19}, - issn = {2352-1791}, - url = {https://www.sciencedirect.com/science/article/pii/S2352179118302758}, - doi = {10.1016/j.nme.2019.03.008}, - abstract = {ITER-grade tungsten (W) specimens were exposed to similar deuterium (D) plasma condition (ion flux density of 6.0 × 1021 D m − 2s−1, D ion fluence of 5.0 × 1025 D m − 2) at the surface temperature of 623 K. Thermal desorption spectroscopy was used to measure total D retention in one W specimen after D plasma exposure. Glow-discharge optical emission spectroscopy was used to measure D depth profiling from the other W specimen exposed to the similar condition, and deep D trapping up to 25 μm was observed. When the normalized D depth profile was used with a reaction-diffusion code TMAP7 to model experimental D desorption behavior, an excellent agreement to experimental results was achieved. The modeling results suggested that the predominate mechanism of the deep D trapping might be D trapping in intrinsic intergranular cracks in ITER-grade W.}, - language = {en}, +@misc{noauthor_periodic_nodate, + title = {Periodic {Table} of the {Finite} {Elements}}, + url = {https://www-users.cse.umn.edu/~arnold/femtable/}, urldate = {2022-05-13}, - journal = {Nuclear Materials and Energy}, - author = {Shimada, M. and Taylor, C. N.}, - month = may, - year = {2019}, - keywords = {Neutron-irradiation, Plasma facing-components, Tritium retention}, - pages = {273--278}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\T47XXBB3\\S2352179118302758.html:text/html}, + file = {Periodic Table of the Finite Elements:D\:\\Logiciels\\data_zotero\\storage\\MVXQWJRP\\femtable.html:text/html}, } @incollection{poirier_correlations_2016, @@ -9326,23 +9494,41 @@ @incollection{poirier_correlations_2016 pages = {247--279}, } -@misc{noauthor_periodic_nodate, - title = {Periodic {Table} of the {Finite} {Elements}}, - url = {https://www-users.cse.umn.edu/~arnold/femtable/}, +@article{shimada_improved_2019, + title = {Improved tritium retention modeling with reaction-diffusion code {TMAP} and bulk depth profiling capability}, + volume = {19}, + issn = {2352-1791}, + url = {https://www.sciencedirect.com/science/article/pii/S2352179118302758}, + doi = {10.1016/j.nme.2019.03.008}, + abstract = {ITER-grade tungsten (W) specimens were exposed to similar deuterium (D) plasma condition (ion flux density of 6.0 × 1021 D m − 2s−1, D ion fluence of 5.0 × 1025 D m − 2) at the surface temperature of 623 K. Thermal desorption spectroscopy was used to measure total D retention in one W specimen after D plasma exposure. Glow-discharge optical emission spectroscopy was used to measure D depth profiling from the other W specimen exposed to the similar condition, and deep D trapping up to 25 μm was observed. When the normalized D depth profile was used with a reaction-diffusion code TMAP7 to model experimental D desorption behavior, an excellent agreement to experimental results was achieved. The modeling results suggested that the predominate mechanism of the deep D trapping might be D trapping in intrinsic intergranular cracks in ITER-grade W.}, + language = {en}, urldate = {2022-05-13}, - file = {Periodic Table of the Finite Elements:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MVXQWJRP\\femtable.html:text/html}, + journal = {Nuclear Materials and Energy}, + author = {Shimada, M. and Taylor, C. N.}, + month = may, + year = {2019}, + keywords = {Neutron-irradiation, Plasma facing-components, Tritium retention}, + pages = {273--278}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\T47XXBB3\\S2352179118302758.html:text/html}, } -@book{logg_automated_2012, - edition = {1}, - title = {Automated {Solution} of {Differential} {Equations} by the {Finite} {Element} {Method}}, - isbn = {978-3-662-50833-6}, - url = {https://link.springer.com/book/10.1007/978-3-642-23099-8}, +@article{yan_numerical_2020, + title = {Numerical {Calculation} on {Recycling} {Ratio} of {Tritium} from {Tungsten} {Wall} {Used} in {Current} {CFETR} {Design}}, + volume = {39}, + issn = {1572-9591}, + url = {https://doi.org/10.1007/s10894-020-00247-4}, + doi = {10.1007/s10894-020-00247-4}, + abstract = {The recycling of tritium from plasma facing wall is an important neutral fuel source (in atomic and molecular form) for plasma confinement and particle control. In this study, the recycling process at tungsten wall based on current CFETR design was modeled. Monte Carlo code SRIM was used to model the implantation of energetic tritium ions into pure tungsten and to get back-scattering fraction of ions and the distribution of implanted tritium ions. The diffusion process of atoms in materials, with recombination at surface as boundary condition, was simulated using numerical approach for both stead and transient state. The total recycling ratio was contributed by fast process (implantation and back scattering) and slow process (diffusion and recombination) and its value nearly equals to 1 for stead state. Temporal dependence of total recycling ratio mainly depended on the slow process and was limited by diffusion coefficient in the bulk near surface and existence of traps in material. For tungsten material with good surface condition, the time of 90\% recycling was characterized as 1 ms and affected by temperature, recombination coefficient and concentration of traps while the thickness of material had less affection. Isotope effect that recycling ratio of tritium was larger than that of deuterium at the same situation was also found in the simulation and this effect may affect particle balance and fueling in D-T plasma operation. A collection of theoretical models to estimate the recycling ratio and its time dependence were also summarized and validated by the simulation results.}, language = {en}, - urldate = {2022-05-17}, - author = {Logg, Anders and Mardal, Kent-Andre and Wells, Garth}, - year = {2012}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\H9C7NS6T\\978-3-642-23099-8.html:text/html}, + number = {4}, + urldate = {2022-05-13}, + journal = {Journal of Fusion Energy}, + author = {Yan, Qiang and Chen, Zhongwen and Wang, Zhijun and Kong, Defeng and Wang, Xiang and Gou, Fujun and Zhang, Kun}, + month = aug, + year = {2020}, + keywords = {Tungsten, Fusion energy, Plasma material interaction, Wall tritium recycling}, + pages = {163--177}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\SG2NE6NS\\Yan et al. - 2020 - Numerical Calculation on Recycling Ratio of Tritiu.pdf:application/pdf}, } @techreport{zweben_effect_2014, @@ -9357,24 +9543,7 @@ @techreport{zweben_effect_2014 year = {2014}, doi = {10.2172/1129011}, pages = {PPPL--4999, 1129011}, - file = {Zweben - 2014 - Effect of Deuterium Gas Puff On The Edge Plasma In.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QUYJSE6K\\Zweben - 2014 - Effect of Deuterium Gas Puff On The Edge Plasma In.pdf:application/pdf}, -} - -@article{harutyunyan_tungsten_2022, - title = {Tungsten fuzz annealing effect on deuterium retention in polycrystalline tungsten}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/S0022311522002975}, - doi = {10.1016/j.jnucmat.2022.153811}, - abstract = {Using a beam-plasma discharge device operating on helium (He), tungsten with the fuzz on the surface (Wf) has been formed by irradiating polycrystalline tungsten (W) samples with the He ions energy of ∼150 eV and the fluence of ∼6 × 1024 He/m2 at the temperature of 1273 K. The deuterium (D) retention in Wf annealed at different temperatures was studied by thermal desorption spectroscopy (TDS). Before and after annealing at temperatures of 1000,1200,1400 and 1600 K, Wf was irradiated at room temperature by 2 keV D3+(667 eV/D) ions with the fluence of 1021 D/m2, then in-situ TDS was performed after each irradiation. Annealing W above 1200 K clearly changes the retention mechanism of D: the TDS spectrum consisting of multiple peaks changes to an almost single-peak spectrum. Annealing at 1600 K leads to surface smoothing and the decrease of the D retention by a factor of two compared to the annealing at 1000 K. This can be explained by an increase of the reflection coefficient for the flat W surface. However, the D retention in Wf is significantly higher compared to that in W without He plasma exposure even after annealing at 1600 K, because there are still He bubbles in Wf that effectively trap D}, - language = {en}, - urldate = {2022-05-30}, - journal = {Journal of Nuclear Materials}, - author = {Harutyunyan, Z. and Ogorodnikova, O. and Gasparyan, Yu. and Efimov, V. and Sorokin, I. and Sergeev, N. and Kanashenko, S.}, - month = may, - year = {2022}, - keywords = {helium, nuclear fusion, hydrogen isotopes, plasmafacing materials, thermal desorption spectroscopy, tungsten fuzz}, - pages = {153811}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\SLCWGBRT\\S0022311522002975.html:text/html}, + file = {Zweben - 2014 - Effect of Deuterium Gas Puff On The Edge Plasma In.pdf:D\:\\Logiciels\\data_zotero\\storage\\QUYJSE6K\\Zweben - 2014 - Effect of Deuterium Gas Puff On The Edge Plasma In.pdf:application/pdf}, } @article{hernandez_study_2021, @@ -9393,153 +9562,44 @@ @article{hernandez_study_2021 year = {2021}, keywords = {Permeation, Deuterium retention and desorption, Ionizing irradiation, SiC coating, Thermal cycling}, pages = {153219}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\6PW8HG3H\\S0022311521004426.html:text/html}, -} - -@article{wu_solubility_1983, - title = {The solubility of deuterium in lithium-lead alloys}, - volume = {114}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/0022311583900697}, - doi = {10.1016/0022-3115(83)90069-7}, - abstract = {The solubility of deuterium in lithium-lead alloys was measured as a function of temperature and atomic fraction of lithium, XLi. It was found that, at the atom fraction XLi = 0.78, corresponding to the composition “Li7Pb2”, the solubility in the solid phase is lower by a factor of a few hundred than that in the liquid phase. The solubility of deuterium in the Li-Pb system decreases drastically with decreasing XLi. At about XLi = 0.17, which corresponds to the eutectic “Li17Pb83”, the solubility is independent of temperature. The transition from exothermal to endothermal dissolution occurred at about XLi ⩽ 0.17.}, - language = {en}, - number = {1}, - urldate = {2022-06-02}, - journal = {Journal of Nuclear Materials}, - author = {Wu, C. H.}, - month = feb, - year = {1983}, - pages = {30--33}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CER32GRB\\0022311583900697.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\6PW8HG3H\\S0022311521004426.html:text/html}, } -@article{chan_thermodynamic_1984, - title = {A thermodynamic investigation of dilute solutions of hydrogen in liquid {Li}-{Pb} alloys}, - volume = {123}, +@article{harutyunyan_tungsten_2022, + title = {Tungsten fuzz annealing effect on deuterium retention in polycrystalline tungsten}, issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/0022311584901983}, - doi = {10.1016/0022-3115(84)90198-3}, - abstract = {Isothermal measurements of hydrogen decomposition pressure (P) vs. hydrogen concentration (XH) were carried out on ten Li-Pb alloys in the composition range 0.1 ≤ XPb ≤ 0.8. Each alloy was investigated at several temperatures from 50 to 400 K above the corresponding liquidus point and at hydrogen pressures up to 15 kPa. Sieverts' law (√P = KXH, as XH → O) was found to be obeyed under these conditions. The Sieverts' constants showed a 105-fold increase as the Pb content was increased over the stated composition range. The InK vs. XPb, data, fitted to a thermodynamic model, yielded a semi-empirical equation which produced (1) Sieverts' constants within the measured temperature and composition ranges, (2) an inflection point at XPb, ∼0.3, presumably caused by the formation of partly ionic Li-Pb bonds, (3) a steady decrease in the temperature coefficient as a function of XPb, resulting in a sign reversal at XPb ∼0.6, and (4) Sieverts' constant estimates for pure liquid lead. Availability of the latter estimates permitted testing of three statistical mechanical models against the experimental data. The results were compared with other literature on the H-Li-Pb system.}, + url = {https://www.sciencedirect.com/science/article/pii/S0022311522002975}, + doi = {10.1016/j.jnucmat.2022.153811}, + abstract = {Using a beam-plasma discharge device operating on helium (He), tungsten with the fuzz on the surface (Wf) has been formed by irradiating polycrystalline tungsten (W) samples with the He ions energy of ∼150 eV and the fluence of ∼6 × 1024 He/m2 at the temperature of 1273 K. The deuterium (D) retention in Wf annealed at different temperatures was studied by thermal desorption spectroscopy (TDS). Before and after annealing at temperatures of 1000,1200,1400 and 1600 K, Wf was irradiated at room temperature by 2 keV D3+(667 eV/D) ions with the fluence of 1021 D/m2, then in-situ TDS was performed after each irradiation. Annealing W above 1200 K clearly changes the retention mechanism of D: the TDS spectrum consisting of multiple peaks changes to an almost single-peak spectrum. Annealing at 1600 K leads to surface smoothing and the decrease of the D retention by a factor of two compared to the annealing at 1000 K. This can be explained by an increase of the reflection coefficient for the flat W surface. However, the D retention in Wf is significantly higher compared to that in W without He plasma exposure even after annealing at 1600 K, because there are still He bubbles in Wf that effectively trap D}, language = {en}, - number = {1}, - urldate = {2022-06-02}, + urldate = {2022-05-30}, journal = {Journal of Nuclear Materials}, - author = {Chan, Y. C. and Veleckis, E.}, + author = {Harutyunyan, Z. and Ogorodnikova, O. and Gasparyan, Yu. and Efimov, V. and Sorokin, I. and Sergeev, N. and Kanashenko, S.}, month = may, - year = {1984}, - pages = {935--940}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\TLTFTVBK\\0022311584901983.html:text/html}, -} - -@article{fauvet_hydrogen_1988, - title = {Hydrogen behaviour in liquid {17Li83Pb} alloy}, - volume = {155-157}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/0022311588903017}, - doi = {10.1016/0022-3115(88)90301-7}, - abstract = {The solubility and the diffusivity of hydrogen in the eutectic alloy 17Li83Pb have been studied in a device especially designed for taking into account the expected low level of solubility. The structural materials were chosen as inert as possible to hydrogen and a large amount of alloy is used. The data obtained at 450°C (Sieverts' constant: (2.7 ± 0.2) × 10−8 atomic fraction. Pa−12; diffusivity: 1.5 × 10−9mm2s−1) confirm the low ability of the alloy 17Li83Pb for containing hydrogen.}, - language = {en}, - urldate = {2022-06-02}, - journal = {Journal of Nuclear Materials}, - author = {Fauvet, P and Sannier, J}, - month = jul, - year = {1988}, - pages = {516--519}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\7JFYMFR2\\0022311588903017.html:text/html}, -} - -@article{schumacher_hydrogen_1990, - title = {Hydrogen {Solubility} in the {Liquid} {Alloys} {Lithium}-{Indium}, {Lithium}-{Lead}, and {Lithium}-{Tin}}, - volume = {94}, - issn = {0005-9021}, - url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/bbpc.19900940612}, - doi = {10.1002/bbpc.19900940612}, - abstract = {Measurements of the hydrogen solubility in liquid alloys of the binary systems Li—In, Li—Pb and Li—Sn are reported. A detailled description of the experimental procedure is given. Solubility data were recorded in the pressure range 150—20000 hPa at temperatures up to 1220 K. Alloy interactions with stainless steel containers and with oxygen impurities were investigated. The temperature and pressure dependence of the mole fraction xH of hydrogen atoms in the melt at low hydrogen concentration, where Sievert's law is valid, can be described by the following equation: ln(xH√105Pa/PH2) = - A + B/T. The values of the constants are A = 8.17, B = 734 K (LiPb); A = 7.84, B = 1970 K (Li62Pb38); A = 7.42, B = 1200 K (LiIn); A = 7.67, B = 3300 K (Li62In38); A = 7.08, B = 600 K (Li57Sn43); A = 6.86, B = 830 K (Li62Sn38). Strong deviations from Sievert's law are observed for two alloys indicating alloy decomposition. The reduction of the excess entropy of dissolved hydrogen in the alloys compared to pure lithium is discussed in the frame of an electrostatic model.}, - language = {en}, - number = {6}, - urldate = {2022-06-02}, - journal = {Berichte der Bunsengesellschaft für physikalische Chemie}, - author = {Schumacher, Richard and Weiss, Alarich}, - year = {1990}, - note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1002/bbpc.19900940612}, - keywords = {Alloys, Gases in Metals, Hydrogen in Metals, Liquid Metals, Thermodynamics}, - pages = {684--691}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\85T3FWBR\\bbpc.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\EJTH36EF\\Schumacher et Weiss - 1990 - Hydrogen Solubility in the Liquid Alloys Lithium-I.pdf:application/pdf}, -} - -@article{reiter_solubility_1991, - title = {Solubility and diffusivity of hydrogen isotopes in liquid {Pb}{17Li}}, - volume = {14}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/0920379691900039}, - doi = {10.1016/0920-3796(91)90003-9}, - abstract = {The results of measurements of solubility S and diffusivity D of hydrogen isotopes in Pb17Li in the temperature range from 508 K to 700 K are presented: SH = √P02.44 × 10−8exp(−1350/RT), SD = √P02.36 × 10−8exp(−1350/RT), ST = √P02.32 × 10−8exp(−1350/RT), D = 4.03 × 10−8exp(−19500/RT), where S is given in atomic fractions, D in m2/s, P0 in Pa, T in K and R = 8.31 J/(mol K). These results are compared with those of other authors.}, - language = {en}, - number = {3}, - urldate = {2022-06-02}, - journal = {Fusion Engineering and Design}, - author = {Reiter, F.}, - month = apr, - year = {1991}, - pages = {207--211}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\MC67H7US\\0920379691900039.html:text/html}, -} - -@article{aiello_determination_2006, - series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, - title = {Determination of hydrogen solubility in lead lithium using sole device}, - volume = {81}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S092037960500565X}, - doi = {10.1016/j.fusengdes.2005.06.364}, - abstract = {In the helium cooled lithium lead (HCLL) blanket for DEMO the breeding material is represented by eutectic lead lithium alloy flowing in poloidal–radial direction in the breeding module. The low solubility of hydrogen isotopes in the alloy generates an high partial pressure and, as a consequence, an high tritium permeation rate from the breeder into the He coolant and a considerable tritium inventory in the structural materials. Several experiments, devoted to determine the hydrogen solubility in lead lithium, have been performed in the past, giving contradictory results. To find a reliable value to be used in the safety analysis and in the design of both the tritium extraction system and the coolant purification system, the solubility of hydrogen (SOLE) experiment was launched in ENEA Brasimone in 2002. The SOLE device is based on the use of the absorption technique. The experimental results are in good agreement with the ones obtained in the past with similar techniques, varying from 1×10−2molm−3Pa−1/2 up to 7×10−2molm−3Pa−1/2. The experimental device and the obtained results are presented and discussed in this paper.}, - language = {en}, - number = {1}, - urldate = {2022-06-02}, - journal = {Fusion Engineering and Design}, - author = {Aiello, A. and Ciampichetti, A. and Benamati, G.}, - month = feb, - year = {2006}, - keywords = {Solubility, Lead lithium}, - pages = {639--644}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\S9UCXU68\\S092037960500565X.html:text/html}, -} - -@article{shibuya_isothermal_1987, - title = {Isothermal release of tritium from neutron-irradiated {Li17Pb83}}, - volume = {150}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/0022311587900067}, - doi = {10.1016/0022-3115(87)90006-7}, - abstract = {Isothermal release experiments were carried out to study the tritium recovery from lithium-lead alloy Li17Pb83 in which tritium was produced by irradiation with thermal neutrons. The experimental results indicate that the tritium recovery was incomplete within two hours at 200 °C. At temperatures above the melting point, the tritium release rates have been significantly increased and found to be controlled by the diffusion in the alloy. The determined diffusion coefficients of tritium in the alloy are 6.6 × 10−6, 7.8 × 10−6 and 9.5 × 10−6cm2/s at 300, 400 and 500°C, respectively.}, - language = {en}, - number = {3}, - urldate = {2022-06-02}, - journal = {Journal of Nuclear Materials}, - author = {Shibuya, Yoshinori and Aida, Masao and Fujii, Yasuhiko and Okamoto, Makoto}, - month = nov, - year = {1987}, - pages = {286--291}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I4RSHXH4\\0022311587900067.html:text/html}, + year = {2022}, + keywords = {helium, nuclear fusion, hydrogen isotopes, plasmafacing materials, thermal desorption spectroscopy, tungsten fuzz}, + pages = {153811}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\SLCWGBRT\\S0022311522002975.html:text/html}, } -@article{terai_diffusion_1992, - title = {Diffusion coefficient of tritium in molten lithium-lead alloy ({Li17Pb83}) under neutron irradiation at elevated temperatures}, - volume = {187}, - issn = {0022-3115}, - url = {https://www.sciencedirect.com/science/article/pii/002231159290504E}, - doi = {10.1016/0022-3115(92)90504-E}, - abstract = {The diffusion coefficient of tritium in molten Li17Pb83 alloy was determined under neutron irradiation at 300–700°C. Tritium residence time in the experimental system decreased with increasing H2 pressure in He sweep gas up to 1000 Pa, and above this limiting concentration it became constant. This result suggests that the tritium release rate was controlled only by the tritium diffusion processes in the molten Li17Pb83 alloy sample and in the Fe sample holder above PH2 = 1000 Pa. From the data on tritium residence time obtained in PH2 = 3000 Pa, the diffusion coefficient of tritium was determined as follows: D/m2s−1 = 2.50 × 10−7exp(−27.0 kJmol−1/RT), which was slightly larger than the other literature values.}, +@article{montupet-leblond_influence_2022, + title = {Influence of traps reversibility on hydrogen permeation and retention in {Eurofer97}}, + volume = {62}, + copyright = {All rights reserved}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/1741-4326/ac6e74}, + doi = {10.1088/1741-4326/ac6e74}, + abstract = {The presence of three trapping sites in Eurofer97 and the diffusion and trapping parameters obtained in a previousarticle are confirmed using an additional thermal desorption spectrometry experiment. Using these parameters, permeation cycles are simulated using the diffusion–reaction code mhims in order to study the influence of each trapping site on the permeation dynamics. The concept of traps reversibility is used to qualify this influence. The analysis indicates that the reversibility of the trapping sites is a key parameter in diffusion and permeation dynamics, which must be accounted for to get accurate predictions of hydrogen inventory and permeation.}, language = {en}, - number = {3}, - urldate = {2022-06-02}, - journal = {Journal of Nuclear Materials}, - author = {Terai, Takayuki and Nagai, Shin'ichi and Yoneoka, Toshiaki and Takahashi, Yoichi}, - month = may, - year = {1992}, - pages = {247--253}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KBJJATFP\\002231159290504E.html:text/html}, + number = {8}, + urldate = {2022-06-07}, + journal = {Nuclear Fusion}, + author = {Montupet-Leblond, F. and Hodille, E. A. and Payet, M. and Delaporte-Mathurin, R. and Bernard, E. and Charles, Y. and Mougenot, J. and Vartanian, S. and Grisolia, C.}, + month = jun, + year = {2022}, + note = {Publisher: IOP Publishing}, + pages = {086011}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\ET4XISBI\\Montupet-Leblond et al. - 2022 - Influence of traps reversibility on hydrogen perme.pdf:application/pdf}, } @article{alberro_experimental_2015, @@ -9556,9 +9616,9 @@ @article{alberro_experimental_2015 author = {Alberro, G. and Peñalva, I. and Sarrionandia-Ibarra, A. and Legarda, F. and Esteban, G. A.}, month = oct, year = {2015}, - keywords = {Diffusivity, Breeding blanket, Experimental values, Sieverts’ constant, Tritium extraction}, + keywords = {Breeding blanket, Diffusivity, Experimental values, Sieverts’ constant, Tritium extraction}, pages = {1919--1923}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5N96XEXM\\S0920379615300119.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\5N96XEXM\\S0920379615300119.html:text/html}, } @article{katsuta_hydrogen_1985, @@ -9575,7 +9635,7 @@ @article{katsuta_hydrogen_1985 month = aug, year = {1985}, pages = {167--170}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\LZFE5J2V\\0022311585901278.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\LZFE5J2V\\0022311585901278.html:text/html}, } @article{zeng_apparatus_2014, @@ -9587,14 +9647,14 @@ @article{zeng_apparatus_2014 author = {Zeng, Youshi and Sheng-Wei, Wu and Yuan, Qian and Guang-Hua, Wang and Lin, Du and Wei, Liu and Zheng-Hai, Xia}, month = aug, year = {2014}, - file = {You-Shi et al. - 2014 - Apparatus for determining permeability of hydrogen.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\BTWRJJGJ\\You-Shi et al. - 2014 - Apparatus for determining permeability of hydrogen.pdf:application/pdf}, + file = {You-Shi et al. - 2014 - Apparatus for determining permeability of hydrogen.pdf:D\:\\Logiciels\\data_zotero\\storage\\BTWRJJGJ\\You-Shi et al. - 2014 - Apparatus for determining permeability of hydrogen.pdf:application/pdf}, } @misc{noauthor_apparatus_nodate, title = {Apparatus for determining permeability of hydrogen isotopes in molten-salt}, url = {http://www.j.sinap.ac.cn/nst/EN/abstract/abstract2123.shtml}, urldate = {2022-06-05}, - file = {Apparatus for determining permeability of hydrogen isotopes in molten-salt:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5ZAZK5AH\\abstract2123.html:text/html}, + file = {Apparatus for determining permeability of hydrogen isotopes in molten-salt:D\:\\Logiciels\\data_zotero\\storage\\5ZAZK5AH\\abstract2123.html:text/html}, } @article{wampler_precipitation_1976, @@ -9612,14 +9672,14 @@ @article{wampler_precipitation_1976 month = jul, year = {1976}, pages = {129--141}, - file = {Wampler et al. - 1976 - Precipitation and trapping of hydrogen in copper.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3W46JGMI\\Wampler et al. - 1976 - Precipitation and trapping of hydrogen in copper.pdf:application/pdf}, + file = {Wampler et al. - 1976 - Precipitation and trapping of hydrogen in copper.pdf:D\:\\Logiciels\\data_zotero\\storage\\3W46JGMI\\Wampler et al. - 1976 - Precipitation and trapping of hydrogen in copper.pdf:application/pdf}, } @misc{noauthor_precipitation_nodate, title = {Precipitation and trapping of hydrogen in copper: {The} {Philosophical} {Magazine}: {A} {Journal} of {Theoretical} {Experimental} and {Applied} {Physics}: {Vol} 34, {No} 1}, url = {https://www.tandfonline.com/doi/abs/10.1080/14786437608228179}, urldate = {2022-06-05}, - file = {Precipitation and trapping of hydrogen in copper\: The Philosophical Magazine\: A Journal of Theoretical Experimental and Applied Physics\: Vol 34, No 1:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\DLKTSUMZ\\14786437608228179.html:text/html}, + file = {Precipitation and trapping of hydrogen in copper\: The Philosophical Magazine\: A Journal of Theoretical Experimental and Applied Physics\: Vol 34, No 1:D\:\\Logiciels\\data_zotero\\storage\\DLKTSUMZ\\14786437608228179.html:text/html}, } @article{thomas_solubility_1967, @@ -9646,9 +9706,9 @@ @article{otsuka_behavior_2010 author = {Otsuka, Teppei and Tanabe, Tetsuo}, month = dec, year = {2010}, - keywords = {Tritium, Diffusion, Trapping, Surface, Release}, + keywords = {Diffusion, Tritium, Trapping, Surface, Release}, pages = {1437--1441}, - file = {Texte intégral:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\YI9V6GF6\\Otsuka et Tanabe - 2010 - Behavior of tritium accumulated on materials surfa.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\CQC4Y7VF\\S0920379610001341.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CQC4Y7VF\\S0920379610001341.html:text/html;Texte intégral:D\:\\Logiciels\\data_zotero\\storage\\YI9V6GF6\\Otsuka et Tanabe - 2010 - Behavior of tritium accumulated on materials surfa.pdf:application/pdf}, } @article{eichenauer_notitle_1965, @@ -9674,7 +9734,7 @@ @article{tanabe_hydrogen_1987 year = {1987}, keywords = {deuterium, aluminum, copper, diffusion, ion driven permeation, nickel, permeation spike}, pages = {305--308}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\I382FP3L\\0022311587903497.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\I382FP3L\\0022311587903497.html:text/html}, } @article{perkins_permeation_1973, @@ -9715,7 +9775,7 @@ @article{katz_diffusion_1971 year = {1971}, note = {Publisher: American Physical Society}, pages = {330--341}, - file = {APS Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\T5W5Q7MA\\PhysRevB.4.html:text/html;Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\A74KDIFR\\4034502-diffusion-sub-sub-sub-single-crystal-ni-cu.html:text/html}, + file = {APS Snapshot:D\:\\Logiciels\\data_zotero\\storage\\T5W5Q7MA\\PhysRevB.4.html:text/html;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\A74KDIFR\\4034502-diffusion-sub-sub-sub-single-crystal-ni-cu.html:text/html}, } @article{esteban_hydrogen_2001, @@ -9733,7 +9793,7 @@ @article{esteban_hydrogen_2001 month = may, year = {2001}, pages = {49--56}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\GLH8I96U\\S002231150100486X.html:text/html}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\GLH8I96U\\S002231150100486X.html:text/html}, } @article{ryabchikov_notitle_1964, @@ -9762,7 +9822,7 @@ @article{zakharov_hydrogen_1975 year = {1975}, keywords = {Hydrogen, Tungsten, Permeability, Hydrogen Permeability, Molybdenum}, pages = {149--153}, - file = {Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\4A7NUX6Q\\Zakharov et al. - 1975 - Hydrogen permeability of polycrystalline and monoc.pdf:application/pdf}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\4A7NUX6Q\\Zakharov et al. - 1975 - Hydrogen permeability of polycrystalline and monoc.pdf:application/pdf}, } @article{moore_adsorptiondesorption_1964, @@ -9781,40 +9841,298 @@ @article{moore_adsorptiondesorption_1964 pages = {2626--2638}, } -@article{heinola_diffusion_2010, - title = {Diffusion of hydrogen in bcc tungsten studied with first principle calculations}, - volume = {107}, - issn = {0021-8979}, - url = {https://aip.scitation.org/doi/10.1063/1.3386515}, - doi = {10.1063/1.3386515}, - number = {11}, - urldate = {2022-06-05}, - journal = {Journal of Applied Physics}, - author = {Heinola, K. and Ahlgren, T.}, - month = jun, - year = {2010}, - note = {Publisher: American Institute of Physics}, - pages = {113531}, +@article{heinola_diffusion_2010, + title = {Diffusion of hydrogen in bcc tungsten studied with first principle calculations}, + volume = {107}, + issn = {0021-8979}, + url = {https://aip.scitation.org/doi/10.1063/1.3386515}, + doi = {10.1063/1.3386515}, + number = {11}, + urldate = {2022-06-05}, + journal = {Journal of Applied Physics}, + author = {Heinola, K. and Ahlgren, T.}, + month = jun, + year = {2010}, + note = {Publisher: American Institute of Physics}, + pages = {113531}, +} + +@article{terai_diffusion_1992, + title = {Diffusion coefficient of tritium in molten lithium-lead alloy ({Li17Pb83}) under neutron irradiation at elevated temperatures}, + volume = {187}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/002231159290504E}, + doi = {10.1016/0022-3115(92)90504-E}, + abstract = {The diffusion coefficient of tritium in molten Li17Pb83 alloy was determined under neutron irradiation at 300–700°C. Tritium residence time in the experimental system decreased with increasing H2 pressure in He sweep gas up to 1000 Pa, and above this limiting concentration it became constant. This result suggests that the tritium release rate was controlled only by the tritium diffusion processes in the molten Li17Pb83 alloy sample and in the Fe sample holder above PH2 = 1000 Pa. From the data on tritium residence time obtained in PH2 = 3000 Pa, the diffusion coefficient of tritium was determined as follows: D/m2s−1 = 2.50 × 10−7exp(−27.0 kJmol−1/RT), which was slightly larger than the other literature values.}, + language = {en}, + number = {3}, + urldate = {2022-06-02}, + journal = {Journal of Nuclear Materials}, + author = {Terai, Takayuki and Nagai, Shin'ichi and Yoneoka, Toshiaki and Takahashi, Yoichi}, + month = may, + year = {1992}, + pages = {247--253}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\KBJJATFP\\002231159290504E.html:text/html}, +} + +@article{shibuya_isothermal_1987, + title = {Isothermal release of tritium from neutron-irradiated {Li17Pb83}}, + volume = {150}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/0022311587900067}, + doi = {10.1016/0022-3115(87)90006-7}, + abstract = {Isothermal release experiments were carried out to study the tritium recovery from lithium-lead alloy Li17Pb83 in which tritium was produced by irradiation with thermal neutrons. The experimental results indicate that the tritium recovery was incomplete within two hours at 200 °C. At temperatures above the melting point, the tritium release rates have been significantly increased and found to be controlled by the diffusion in the alloy. The determined diffusion coefficients of tritium in the alloy are 6.6 × 10−6, 7.8 × 10−6 and 9.5 × 10−6cm2/s at 300, 400 and 500°C, respectively.}, + language = {en}, + number = {3}, + urldate = {2022-06-02}, + journal = {Journal of Nuclear Materials}, + author = {Shibuya, Yoshinori and Aida, Masao and Fujii, Yasuhiko and Okamoto, Makoto}, + month = nov, + year = {1987}, + pages = {286--291}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\I4RSHXH4\\0022311587900067.html:text/html}, +} + +@article{aiello_determination_2006, + series = {Proceedings of the {Seventh} {International} {Symposium} on {Fusion} {Nuclear} {Technology}}, + title = {Determination of hydrogen solubility in lead lithium using sole device}, + volume = {81}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S092037960500565X}, + doi = {10.1016/j.fusengdes.2005.06.364}, + abstract = {In the helium cooled lithium lead (HCLL) blanket for DEMO the breeding material is represented by eutectic lead lithium alloy flowing in poloidal–radial direction in the breeding module. The low solubility of hydrogen isotopes in the alloy generates an high partial pressure and, as a consequence, an high tritium permeation rate from the breeder into the He coolant and a considerable tritium inventory in the structural materials. Several experiments, devoted to determine the hydrogen solubility in lead lithium, have been performed in the past, giving contradictory results. To find a reliable value to be used in the safety analysis and in the design of both the tritium extraction system and the coolant purification system, the solubility of hydrogen (SOLE) experiment was launched in ENEA Brasimone in 2002. The SOLE device is based on the use of the absorption technique. The experimental results are in good agreement with the ones obtained in the past with similar techniques, varying from 1×10−2molm−3Pa−1/2 up to 7×10−2molm−3Pa−1/2. The experimental device and the obtained results are presented and discussed in this paper.}, + language = {en}, + number = {1}, + urldate = {2022-06-02}, + journal = {Fusion Engineering and Design}, + author = {Aiello, A. and Ciampichetti, A. and Benamati, G.}, + month = feb, + year = {2006}, + keywords = {Solubility, Lead lithium}, + pages = {639--644}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\S9UCXU68\\S092037960500565X.html:text/html}, +} + +@article{reiter_solubility_1991, + title = {Solubility and diffusivity of hydrogen isotopes in liquid {Pb}{17Li}}, + volume = {14}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/0920379691900039}, + doi = {10.1016/0920-3796(91)90003-9}, + abstract = {The results of measurements of solubility S and diffusivity D of hydrogen isotopes in Pb17Li in the temperature range from 508 K to 700 K are presented: SH = √P02.44 × 10−8exp(−1350/RT), SD = √P02.36 × 10−8exp(−1350/RT), ST = √P02.32 × 10−8exp(−1350/RT), D = 4.03 × 10−8exp(−19500/RT), where S is given in atomic fractions, D in m2/s, P0 in Pa, T in K and R = 8.31 J/(mol K). These results are compared with those of other authors.}, + language = {en}, + number = {3}, + urldate = {2022-06-02}, + journal = {Fusion Engineering and Design}, + author = {Reiter, F.}, + month = apr, + year = {1991}, + pages = {207--211}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\MC67H7US\\0920379691900039.html:text/html}, +} + +@article{schumacher_hydrogen_1990, + title = {Hydrogen {Solubility} in the {Liquid} {Alloys} {Lithium}-{Indium}, {Lithium}-{Lead}, and {Lithium}-{Tin}}, + volume = {94}, + issn = {0005-9021}, + url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/bbpc.19900940612}, + doi = {10.1002/bbpc.19900940612}, + abstract = {Measurements of the hydrogen solubility in liquid alloys of the binary systems Li—In, Li—Pb and Li—Sn are reported. A detailled description of the experimental procedure is given. Solubility data were recorded in the pressure range 150—20000 hPa at temperatures up to 1220 K. Alloy interactions with stainless steel containers and with oxygen impurities were investigated. The temperature and pressure dependence of the mole fraction xH of hydrogen atoms in the melt at low hydrogen concentration, where Sievert's law is valid, can be described by the following equation: ln(xH√105Pa/PH2) = - A + B/T. The values of the constants are A = 8.17, B = 734 K (LiPb); A = 7.84, B = 1970 K (Li62Pb38); A = 7.42, B = 1200 K (LiIn); A = 7.67, B = 3300 K (Li62In38); A = 7.08, B = 600 K (Li57Sn43); A = 6.86, B = 830 K (Li62Sn38). Strong deviations from Sievert's law are observed for two alloys indicating alloy decomposition. The reduction of the excess entropy of dissolved hydrogen in the alloys compared to pure lithium is discussed in the frame of an electrostatic model.}, + language = {en}, + number = {6}, + urldate = {2022-06-02}, + journal = {Berichte der Bunsengesellschaft für physikalische Chemie}, + author = {Schumacher, Richard and Weiss, Alarich}, + year = {1990}, + note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1002/bbpc.19900940612}, + keywords = {Alloys, Gases in Metals, Hydrogen in Metals, Liquid Metals, Thermodynamics}, + pages = {684--691}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\EJTH36EF\\Schumacher et Weiss - 1990 - Hydrogen Solubility in the Liquid Alloys Lithium-I.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\85T3FWBR\\bbpc.html:text/html}, +} + +@article{fauvet_hydrogen_1988, + title = {Hydrogen behaviour in liquid {17Li83Pb} alloy}, + volume = {155-157}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/0022311588903017}, + doi = {10.1016/0022-3115(88)90301-7}, + abstract = {The solubility and the diffusivity of hydrogen in the eutectic alloy 17Li83Pb have been studied in a device especially designed for taking into account the expected low level of solubility. The structural materials were chosen as inert as possible to hydrogen and a large amount of alloy is used. The data obtained at 450°C (Sieverts' constant: (2.7 ± 0.2) × 10−8 atomic fraction. Pa−12; diffusivity: 1.5 × 10−9mm2s−1) confirm the low ability of the alloy 17Li83Pb for containing hydrogen.}, + language = {en}, + urldate = {2022-06-02}, + journal = {Journal of Nuclear Materials}, + author = {Fauvet, P and Sannier, J}, + month = jul, + year = {1988}, + pages = {516--519}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\7JFYMFR2\\0022311588903017.html:text/html}, +} + +@article{chan_thermodynamic_1984, + title = {A thermodynamic investigation of dilute solutions of hydrogen in liquid {Li}-{Pb} alloys}, + volume = {123}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/0022311584901983}, + doi = {10.1016/0022-3115(84)90198-3}, + abstract = {Isothermal measurements of hydrogen decomposition pressure (P) vs. hydrogen concentration (XH) were carried out on ten Li-Pb alloys in the composition range 0.1 ≤ XPb ≤ 0.8. Each alloy was investigated at several temperatures from 50 to 400 K above the corresponding liquidus point and at hydrogen pressures up to 15 kPa. Sieverts' law (√P = KXH, as XH → O) was found to be obeyed under these conditions. The Sieverts' constants showed a 105-fold increase as the Pb content was increased over the stated composition range. The InK vs. XPb, data, fitted to a thermodynamic model, yielded a semi-empirical equation which produced (1) Sieverts' constants within the measured temperature and composition ranges, (2) an inflection point at XPb, ∼0.3, presumably caused by the formation of partly ionic Li-Pb bonds, (3) a steady decrease in the temperature coefficient as a function of XPb, resulting in a sign reversal at XPb ∼0.6, and (4) Sieverts' constant estimates for pure liquid lead. Availability of the latter estimates permitted testing of three statistical mechanical models against the experimental data. The results were compared with other literature on the H-Li-Pb system.}, + language = {en}, + number = {1}, + urldate = {2022-06-02}, + journal = {Journal of Nuclear Materials}, + author = {Chan, Y. C. and Veleckis, E.}, + month = may, + year = {1984}, + pages = {935--940}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\TLTFTVBK\\0022311584901983.html:text/html}, +} + +@article{wu_solubility_1983, + title = {The solubility of deuterium in lithium-lead alloys}, + volume = {114}, + issn = {0022-3115}, + url = {https://www.sciencedirect.com/science/article/pii/0022311583900697}, + doi = {10.1016/0022-3115(83)90069-7}, + abstract = {The solubility of deuterium in lithium-lead alloys was measured as a function of temperature and atomic fraction of lithium, XLi. It was found that, at the atom fraction XLi = 0.78, corresponding to the composition “Li7Pb2”, the solubility in the solid phase is lower by a factor of a few hundred than that in the liquid phase. The solubility of deuterium in the Li-Pb system decreases drastically with decreasing XLi. At about XLi = 0.17, which corresponds to the eutectic “Li17Pb83”, the solubility is independent of temperature. The transition from exothermal to endothermal dissolution occurred at about XLi ⩽ 0.17.}, + language = {en}, + number = {1}, + urldate = {2022-06-02}, + journal = {Journal of Nuclear Materials}, + author = {Wu, C. H.}, + month = feb, + year = {1983}, + pages = {30--33}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\CER32GRB\\0022311583900697.html:text/html}, +} + +@article{webster_fusion_2003, + title = {Fusion: {Power} for the future}, + volume = {38}, + issn = {0031-9120}, + shorttitle = {Fusion}, + url = {https://doi.org/10.1088/0031-9120/38/2/305}, + doi = {10.1088/0031-9120/38/2/305}, + abstract = {There is a growing recognition that we need an alternative to conventional fossil fuels. Shortages of oil and gas have the potential to cause economic and political instability, and burning fossil fuels can cause environmental damage, as well as being the likeliest cause of global warming. Fusion - the process that powers the sun and stars, has the potential to provide large-scale, safe energy production, without adding to global warming and without the long-term radioactive waste associated with conventional fission power stations. More importantly, within the next 20 years large-scale fusion power production is planned to be demonstrated by the multinational experiment ITER, and a proposed `fast track' to fusion envisages a time-scale of roughly 30 years for a prototype power plant PROTO to be built.}, + language = {en}, + number = {2}, + urldate = {2022-06-08}, + journal = {Physics Education}, + author = {Webster, Anthony J.}, + month = mar, + year = {2003}, + note = {Publisher: IOP Publishing}, + pages = {135--142}, +} + +@book{mccracken_fusion_2013, + address = {Boston}, + title = {Fusion ({Second} {Edition})}, + isbn = {978-0-12-384656-3}, + url = {http://www.gammaexplorer.com/wp-content/uploads/2014/03/Fusion-The-Energy-of-the-Universe.pdf}, + language = {en}, + urldate = {2022-06-08}, + publisher = {Academic Press}, + editor = {McCracken, Garry and Stott, Peter}, + month = jan, + year = {2013}, + doi = {10.1016/B978-0-12-384656-3.00015-5}, + file = {Fusion-The-Energy-of-the-Universe.pdf:D\:\\Logiciels\\data_zotero\\storage\\HH7RHB97\\Fusion-The-Energy-of-the-Universe.pdf:application/pdf;ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XX8YCY6R\\B9780123846563000155.html:text/html}, +} + +@techreport{forrest_fendl-3_2012, + address = {International Atomic Energy Agency (IAEA)}, + title = {{FENDL}-3 {Library} - {Summary} {Documentation}}, + abstract = {Nuclear fusion is recognised as a long-term energy source The IAEA has played an important +role in nurturing the work on this future energy source by providing support for the +exchange of scientific and technical information on fusion research through conferences, +meetings and projects The most important initiative on fusion research is currently +the ITER project, and in order to design this and ensure safe operation a wide range +of Nuclear Data information is fundamental Realisation that the needs of nuclear data +for fusion are different from those of fission meant that it was appropriate to produce +a specific data library to address these needs The Fusion Evaluation Nuclear Data +Library (FENDL) was the response of the IAEA to the need for a data library specifically +designed for fusion applications An initial meeting was held in 1989 and following +the creation and testing of FENDL-1 in 1995 work started on FENDL-2 This work culminated +in the release of the library FENDL-2 containing evaluations judged to be the best +available in February 1997}, + author = {Forrest, R.A. and Capote, R. and Otsuka, N. and Kawano, T. and Koning, A.J. and Kunieda, S. and Sublet, J-Ch. and Watanabe, Y.}, + year = {2012}, + note = {INDC(NDS)--0628 +INIS Reference Number: 44045168}, + pages = {26}, +} + +@article{casper_development_2013, + title = {Development of the {ITER} baseline inductive scenario}, + volume = {54}, + issn = {0029-5515}, + url = {https://doi.org/10.1088/0029-5515/54/1/013005}, + doi = {10.1088/0029-5515/54/1/013005}, + abstract = {Sustainment of Q ∼ 10 operation with a fusion power of ∼500 MW for several hundred seconds is a key mission goal of the ITER Project. Past calculations and simulations predict that these conditions can be produced in high-confinement mode operation (H-mode) at 15 MA relying on only inductive current drive. Earlier development of 15 MA baseline inductive plasma scenarios provided a focal point for the ITER Design Review conducted in 2007–2008. In the intervening period, detailed predictive simulations, supported by experimental demonstrations in existing tokamaks, allow us to assemble an end-to-end specification of this scenario consistent with the final design of the ITER device. Simulations have encompassed plasma initiation, current ramp-up, plasma burn and current ramp-down, and have included density profiles and thermal transport models producing temperature profiles consistent with edge pedestal conditions present in current fusion experiments. These quasi-stationary conditions are maintained due to the presence of edge-localized modes that limit the edge pressure. High temperatures and densities in the pedestal region produce significant edge bootstrap current that must be considered in modelling of feedback control of shape and vertical stability. In this paper we present new results of transport simulations fully consistent with the final ITER design that remain within allowed limits for the coil system and power supplies. These self-consistent simulations increase our confidence in meeting the challenges of the ITER program.}, + language = {en}, + number = {1}, + urldate = {2022-06-08}, + journal = {Nuclear Fusion}, + author = {Casper, T. and Gribov, Y. and Kavin, A. and Lukash, V. and Khayrutdinov, R. and Fujieda, H. and Kessel, C. and {and}}, + month = dec, + year = {2013}, + note = {Publisher: IOP Publishing}, + pages = {013005}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3ZZ487P3\\Casper et al. - 2013 - Development of the ITER baseline inductive scenari.pdf:application/pdf}, +} + +@article{federici_overview_2014, + series = {Proceedings of the 11th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-11 ({ISFNT}-11) {Barcelona}, {Spain}, 15-20 {September}, 2013}, + title = {Overview of {EU} {DEMO} design and {R}\&{D} activities}, + volume = {89}, + issn = {0920-3796}, + url = {https://www.sciencedirect.com/science/article/pii/S0920379614000714}, + doi = {10.1016/j.fusengdes.2014.01.070}, + abstract = {One important objective of the EU fusion roadmap Horizon 2020 is to lay the foundation of a Demonstration Fusion Power Reactor (DEMO) to follow ITER, with the capability of generating several 100MW of net electricity to the grid and operating with a closed fuel-cycle by 2050. This is currently viewed by many of the nations engaged in the construction of ITER as the remaining crucial step towards the exploitation of fusion power. This paper outlines the DEMO design and R\&D approach that is being adopted in Europe and presents some of the preliminary design options that are under evaluation as well as the most urgent R\&D work that is expected to be launched in the near-future. The R\&D on materials for a near-term DEMO is discussed in detail elsewhere.}, + language = {en}, + number = {7}, + urldate = {2022-06-08}, + journal = {Fusion Engineering and Design}, + author = {Federici, G. and Kemp, R. and Ward, D. and Bachmann, C. and Franke, T. and Gonzalez, S. and Lowry, C. and Gadomska, M. and Harman, J. and Meszaros, B. and Morlock, C. and Romanelli, F. and Wenninger, R.}, + month = oct, + year = {2014}, + keywords = {Systems code, DEMO, Breeding blanket, Divertor, Fusion reactors, Fusion roadmap}, + pages = {882--889}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\QBTEL4QL\\S0920379614000714.html:text/html}, +} + +@incollection{wilson_steppathway_2020, + title = {{STEP}—on the pathway to fusion commercialization}, + isbn = {978-0-7503-2719-0}, + author = {Wilson, Howard and Chapman, Ian and Denton, Tris and Morris, William and Patel, Bhavin and Voss, Garry and Waldon, Chris and Team, the}, + month = dec, + year = {2020}, + doi = {10.1088/978-0-7503-2719-0ch8}, } -@article{montupet-leblond_influence_2022, - title = {Influence of traps reversibility on hydrogen permeation and retention in {Eurofer97}}, - volume = {62}, - copyright = {All rights reserved}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/1741-4326/ac6e74}, - doi = {10.1088/1741-4326/ac6e74}, - abstract = {The presence of three trapping sites in Eurofer97 and the diffusion and trapping parameters obtained in a previousarticle are confirmed using an additional thermal desorption spectrometry experiment. Using these parameters, permeation cycles are simulated using the diffusion–reaction code mhims in order to study the influence of each trapping site on the permeation dynamics. The concept of traps reversibility is used to qualify this influence. The analysis indicates that the reversibility of the trapping sites is a key parameter in diffusion and permeation dynamics, which must be accounted for to get accurate predictions of hydrogen inventory and permeation.}, - language = {en}, - number = {8}, - urldate = {2022-06-07}, - journal = {Nuclear Fusion}, - author = {Montupet-Leblond, F. and Hodille, E. A. and Payet, M. and Delaporte-Mathurin, R. and Bernard, E. and Charles, Y. and Mougenot, J. and Vartanian, S. and Grisolia, C.}, +@book{nuttall_commercialising_2020, + title = {Commercialising {Fusion} {Energy}: {How} small businesses are transforming big science}, + isbn = {978-0-7503-2719-0}, + shorttitle = {Commercialising {Fusion} {Energy}}, + url = {https://iopscience.iop.org/book/978-0-7503-2719-0}, + urldate = {2022-06-08}, + publisher = {IOP Publishing}, + editor = {Nuttall, William J and Konishi, Satoshi and Takeda, Shutaro and Webbe-Wood, David}, + month = dec, + year = {2020}, + doi = {10.1088/978-0-7503-2719-0}, +} + +@misc{delaporte-mathurin_remdelaportemathurinfusion-world_2022, + title = {{RemDelaporteMathurin}/fusion-world: {Patch} 0.4.1}, + copyright = {Open Access}, + shorttitle = {{RemDelaporteMathurin}/fusion-world}, + url = {https://zenodo.org/record/6624244}, + abstract = {What's Changed Remove doublon Pegasus-III by @RemDelaporteMathurin in https://github.com/RemDelaporteMathurin/fusion-world/pull/41 Corrected location of W7X by @RemDelaporteMathurin in https://github.com/RemDelaporteMathurin/fusion-world/pull/42 {\textless}strong{\textgreater}Full Changelog{\textless}/strong{\textgreater}: https://github.com/RemDelaporteMathurin/fusion-world/compare/v0.4...v0.4.1}, + urldate = {2022-06-08}, + publisher = {Zenodo}, + author = {Delaporte-Mathurin, Rémi and Nicolasialovega}, month = jun, year = {2022}, - note = {Publisher: IOP Publishing}, - pages = {086011}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\ET4XISBI\\Montupet-Leblond et al. - 2022 - Influence of traps reversibility on hydrogen perme.pdf:application/pdf}, + doi = {10.5281/ZENODO.6624244}, } @article{zylstra_burning_2022, @@ -9834,25 +10152,26 @@ @article{zylstra_burning_2022 year = {2022}, keywords = {Laser-produced plasmas, Nuclear fusion and fission}, pages = {542--548}, - file = {Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XQDWLCFW\\s41586-021-04281-w.html:text/html;Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\KTIJMWML\\Zylstra et al. - 2022 - Burning plasma achieved in inertial fusion.pdf:application/pdf}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\KTIJMWML\\Zylstra et al. - 2022 - Burning plasma achieved in inertial fusion.pdf:application/pdf;Snapshot:D\:\\Logiciels\\data_zotero\\storage\\XQDWLCFW\\s41586-021-04281-w.html:text/html}, } -@article{jordan_half-life_1967, - title = {Half-life of tritium}, - volume = {29}, - issn = {0022-1902}, - url = {https://www.sciencedirect.com/science/article/pii/0022190267802653}, - doi = {10.1016/0022-1902(67)80265-3}, - abstract = {The half-life of tritium was determined by calorimetry to be 12·346 ± 0·002 yr (probable error by external consistency) by following the decay energy of two samples over a 6-yr period.}, +@article{miquel_laser_2016, + title = {The {Laser} {Mega}-{Joule} : {LMJ} \&\${\textbackslash}mathsemicolon\$ {PETAL} status and {Program} {Overview}}, + volume = {688}, + issn = {1742-6596}, + shorttitle = {The {Laser} {Mega}-{Joule}}, + url = {https://doi.org/10.1088/1742-6596/688/1/012067}, + doi = {10.1088/1742-6596/688/1/012067}, + abstract = {The laser Megajoule (LMJ), developed by the French Commissariat à l'Energie Atomique et aux Energies Alternatives (CEA), will be a cornerstone of the French Simulation Program, which combines improvement of physics models, high performance numerical simulation, and experimental validation. The LMJ facility is under construction at CEA CESTA near Bordeaux and will provide the experimental capabilities to study High-Energy Density Physics (HEDP). One of its goals is to obtain ignition and burn of DT-filled capsules imploded, through indirect drive scheme, inside rugby-shape hohlraum. The PETAL project consists in the addition of one short-pulse (ps) ultra-high-power, high-energy beam (kJ) to the LMJ facility. PETAL will offer a combination of a very high intensity multi-petawatt beam, synchronized with the nanosecond beams of the LMJ. This combination will expand the LMJ experimental field on HEDP. This paper presents an update of LMJ \& PETAL status, together with the development of the overall program including targets, plasma diagnostics and simulation tools.}, language = {en}, - number = {9}, urldate = {2022-06-08}, - journal = {Journal of Inorganic and Nuclear Chemistry}, - author = {Jordan, K. C. and Blanke, B. C. and Dudley, W. A.}, - month = sep, - year = {1967}, - pages = {2129--2131}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\W4PUNC4C\\0022190267802653.html:text/html}, + journal = {Journal of Physics: Conference Series}, + author = {Miquel, J.-L. and Lion, C. and Vivini, P.}, + month = mar, + year = {2016}, + note = {Publisher: IOP Publishing}, + pages = {012067}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\5WBITC8P\\Miquel et al. - 2016 - The Laser Mega-Joule LMJ &\$mathsemicolon\$ PE.pdf:application/pdf}, } @article{mailloux_overview_2022, @@ -9866,163 +10185,67 @@ @article{mailloux_overview_2022 number = {4}, urldate = {2022-06-08}, journal = {Nuclear Fusion}, - author = {Mailloux, J. and Abid, N. and Abraham, K. and Abreu}, + author = {Mailloux, J. and Abid, N. and Abraham, K. and Abreu, P. and Adabonyan, O.}, month = apr, year = {2022}, note = {Publisher: IOP Publishing}, pages = {042026}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3LJK2HV7\\Mailloux et al. - 2022 - Overview of JET results for optimising ITER operat.pdf:application/pdf}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\3LJK2HV7\\Mailloux et al. - 2022 - Overview of JET results for optimising ITER operat.pdf:application/pdf}, } -@article{miquel_laser_2016, - title = {The {Laser} {Mega}-{Joule} : {LMJ} \&\${\textbackslash}mathsemicolon\$ {PETAL} status and {Program} {Overview}}, - volume = {688}, - issn = {1742-6596}, - shorttitle = {The {Laser} {Mega}-{Joule}}, - url = {https://doi.org/10.1088/1742-6596/688/1/012067}, - doi = {10.1088/1742-6596/688/1/012067}, - abstract = {The laser Megajoule (LMJ), developed by the French Commissariat à l'Energie Atomique et aux Energies Alternatives (CEA), will be a cornerstone of the French Simulation Program, which combines improvement of physics models, high performance numerical simulation, and experimental validation. The LMJ facility is under construction at CEA CESTA near Bordeaux and will provide the experimental capabilities to study High-Energy Density Physics (HEDP). One of its goals is to obtain ignition and burn of DT-filled capsules imploded, through indirect drive scheme, inside rugby-shape hohlraum. The PETAL project consists in the addition of one short-pulse (ps) ultra-high-power, high-energy beam (kJ) to the LMJ facility. PETAL will offer a combination of a very high intensity multi-petawatt beam, synchronized with the nanosecond beams of the LMJ. This combination will expand the LMJ experimental field on HEDP. This paper presents an update of LMJ \& PETAL status, together with the development of the overall program including targets, plasma diagnostics and simulation tools.}, +@article{jordan_half-life_1967, + title = {Half-life of tritium}, + volume = {29}, + issn = {0022-1902}, + url = {https://www.sciencedirect.com/science/article/pii/0022190267802653}, + doi = {10.1016/0022-1902(67)80265-3}, + abstract = {The half-life of tritium was determined by calorimetry to be 12·346 ± 0·002 yr (probable error by external consistency) by following the decay energy of two samples over a 6-yr period.}, language = {en}, + number = {9}, urldate = {2022-06-08}, - journal = {Journal of Physics: Conference Series}, - author = {Miquel, J.-L. and Lion, C. and Vivini, P.}, - month = mar, - year = {2016}, - note = {Publisher: IOP Publishing}, - pages = {012067}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\5WBITC8P\\Miquel et al. - 2016 - The Laser Mega-Joule LMJ &\$mathsemicolon\$ PE.pdf:application/pdf}, + journal = {Journal of Inorganic and Nuclear Chemistry}, + author = {Jordan, K. C. and Blanke, B. C. and Dudley, W. A.}, + month = sep, + year = {1967}, + pages = {2129--2131}, + file = {ScienceDirect Snapshot:D\:\\Logiciels\\data_zotero\\storage\\W4PUNC4C\\0022190267802653.html:text/html}, } -@misc{delaporte-mathurin_remdelaportemathurinfusion-world_2022, - title = {{RemDelaporteMathurin}/fusion-world: {Patch} 0.4.1}, - copyright = {Open Access}, - shorttitle = {{RemDelaporteMathurin}/fusion-world}, - url = {https://zenodo.org/record/6624244}, - abstract = {What's Changed Remove doublon Pegasus-III by @RemDelaporteMathurin in https://github.com/RemDelaporteMathurin/fusion-world/pull/41 Corrected location of W7X by @RemDelaporteMathurin in https://github.com/RemDelaporteMathurin/fusion-world/pull/42 {\textless}strong{\textgreater}Full Changelog{\textless}/strong{\textgreater}: https://github.com/RemDelaporteMathurin/fusion-world/compare/v0.4...v0.4.1}, - urldate = {2022-06-08}, - publisher = {Zenodo}, - author = {Delaporte-Mathurin, Rémi and Nicolasialovega}, +@article{wurzel_progress_2022, + title = {Progress toward fusion energy breakeven and gain as measured against the {Lawson} criterion}, + volume = {29}, + issn = {1070-664X}, + url = {https://aip.scitation.org/doi/10.1063/5.0083990}, + doi = {10.1063/5.0083990}, + abstract = {The Lawson criterion is a key concept in the pursuit of fusion energy, relating the fuel density n, pulse duration τ or energy confinement time τE, and fuel temperature T to the energy gain Q of a fusion plasma. The purpose of this paper is to explain and review the Lawson criterion and to provide a compilation of achieved parameters for a broad range of historical and contemporary fusion experiments. Although this paper focuses on the Lawson criterion, it is only one of many equally important factors in assessing the progress and ultimate likelihood of any fusion concept becoming a commercially viable fusion-energy system. Only experimentally measured or inferred values of n, τ or τE, and T that have been published in the peer-reviewed literature are included in this paper, unless noted otherwise. For extracting these parameters, we discuss methodologies that are necessarily specific to different fusion approaches (including magnetic, inertial, and magneto-inertial fusion). This paper is intended to serve as a reference for fusion researchers and a tutorial for all others interested in fusion energy.}, + number = {6}, + urldate = {2022-06-09}, + journal = {Physics of Plasmas}, + author = {Wurzel, Samuel E. and Hsu, Scott C.}, month = jun, year = {2022}, - doi = {10.5281/ZENODO.6624244}, -} - -@book{nuttall_commercialising_2020, - title = {Commercialising {Fusion} {Energy}: {How} small businesses are transforming big science}, - isbn = {978-0-7503-2719-0}, - shorttitle = {Commercialising {Fusion} {Energy}}, - url = {https://iopscience.iop.org/book/978-0-7503-2719-0}, - urldate = {2022-06-08}, - publisher = {IOP Publishing}, - editor = {Nuttall, William J and Konishi, Satoshi and Takeda, Shutaro and Webbe-Wood, David}, - month = dec, - year = {2020}, - doi = {10.1088/978-0-7503-2719-0}, -} - -@incollection{wilson_steppathway_2020, - title = {{STEP}—on the pathway to fusion commercialization}, - isbn = {978-0-7503-2719-0}, - author = {Wilson, Howard and Chapman, Ian and Denton, Tris and Morris, William and Patel, Bhavin and Voss, Garry and Waldon, Chris and Team, the}, - month = dec, - year = {2020}, - doi = {10.1088/978-0-7503-2719-0ch8}, -} - -@article{federici_overview_2014, - series = {Proceedings of the 11th {International} {Symposium} on {Fusion} {Nuclear} {Technology}-11 ({ISFNT}-11) {Barcelona}, {Spain}, 15-20 {September}, 2013}, - title = {Overview of {EU} {DEMO} design and {R}\&{D} activities}, - volume = {89}, - issn = {0920-3796}, - url = {https://www.sciencedirect.com/science/article/pii/S0920379614000714}, - doi = {10.1016/j.fusengdes.2014.01.070}, - abstract = {One important objective of the EU fusion roadmap Horizon 2020 is to lay the foundation of a Demonstration Fusion Power Reactor (DEMO) to follow ITER, with the capability of generating several 100MW of net electricity to the grid and operating with a closed fuel-cycle by 2050. This is currently viewed by many of the nations engaged in the construction of ITER as the remaining crucial step towards the exploitation of fusion power. This paper outlines the DEMO design and R\&D approach that is being adopted in Europe and presents some of the preliminary design options that are under evaluation as well as the most urgent R\&D work that is expected to be launched in the near-future. The R\&D on materials for a near-term DEMO is discussed in detail elsewhere.}, - language = {en}, - number = {7}, - urldate = {2022-06-08}, - journal = {Fusion Engineering and Design}, - author = {Federici, G. and Kemp, R. and Ward, D. and Bachmann, C. and Franke, T. and Gonzalez, S. and Lowry, C. and Gadomska, M. and Harman, J. and Meszaros, B. and Morlock, C. and Romanelli, F. and Wenninger, R.}, - month = oct, - year = {2014}, - keywords = {DEMO, Divertor, Systems code, Breeding blanket, Fusion reactors, Fusion roadmap}, - pages = {882--889}, - file = {ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\QBTEL4QL\\S0920379614000714.html:text/html}, + note = {Publisher: American Institute of Physics}, + pages = {062103}, + file = {Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\MCFYV8T2\\Wurzel et Hsu - 2022 - Progress toward fusion energy breakeven and gain a.pdf:application/pdf}, } -@article{casper_development_2013, - title = {Development of the {ITER} baseline inductive scenario}, - volume = {54}, - issn = {0029-5515}, - url = {https://doi.org/10.1088/0029-5515/54/1/013005}, - doi = {10.1088/0029-5515/54/1/013005}, - abstract = {Sustainment of Q ∼ 10 operation with a fusion power of ∼500 MW for several hundred seconds is a key mission goal of the ITER Project. Past calculations and simulations predict that these conditions can be produced in high-confinement mode operation (H-mode) at 15 MA relying on only inductive current drive. Earlier development of 15 MA baseline inductive plasma scenarios provided a focal point for the ITER Design Review conducted in 2007–2008. In the intervening period, detailed predictive simulations, supported by experimental demonstrations in existing tokamaks, allow us to assemble an end-to-end specification of this scenario consistent with the final design of the ITER device. Simulations have encompassed plasma initiation, current ramp-up, plasma burn and current ramp-down, and have included density profiles and thermal transport models producing temperature profiles consistent with edge pedestal conditions present in current fusion experiments. These quasi-stationary conditions are maintained due to the presence of edge-localized modes that limit the edge pressure. High temperatures and densities in the pedestal region produce significant edge bootstrap current that must be considered in modelling of feedback control of shape and vertical stability. In this paper we present new results of transport simulations fully consistent with the final ITER design that remain within allowed limits for the coil system and power supplies. These self-consistent simulations increase our confidence in meeting the challenges of the ITER program.}, +@article{lawson_criteria_1957, + title = {Some {Criteria} for a {Power} {Producing} {Thermonuclear} {Reactor}}, + volume = {70}, + issn = {0370-1301}, + url = {https://doi.org/10.1088/0370-1301/70/1/303}, + doi = {10.1088/0370-1301/70/1/303}, + abstract = {Calculations of the power balance in thermonuclear reactors operating under various idealized conditions are given. Two classes of reactor are considered: first, self-sustaining systems in which the charged reaction products are trapped and, secondly, pulsed systems in which all the reaction products escape so that energy must be supplied continuously during the pulse. It is found that not only must the temperature be sufficiently high, but also the reaction must be sustained long enough for a definite fraction of the fuel to be burnt.}, language = {en}, number = {1}, - urldate = {2022-06-08}, - journal = {Nuclear Fusion}, - author = {Casper, T. and Gribov, Y. and Kavin, A. and Lukash, V. and Khayrutdinov, R. and Fujieda, H. and Kessel, C. and {and}}, - month = dec, - year = {2013}, - note = {Publisher: IOP Publishing}, - pages = {013005}, - file = {IOP Full Text PDF:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\3ZZ487P3\\Casper et al. - 2013 - Development of the ITER baseline inductive scenari.pdf:application/pdf}, -} - -@techreport{forrest_fendl-3_2012, - address = {International Atomic Energy Agency (IAEA)}, - title = {{FENDL}-3 {Library} - {Summary} {Documentation}}, - abstract = {Nuclear fusion is recognised as a long-term energy source The IAEA has played an important -role in nurturing the work on this future energy source by providing support for the -exchange of scientific and technical information on fusion research through conferences, -meetings and projects The most important initiative on fusion research is currently -the ITER project, and in order to design this and ensure safe operation a wide range -of Nuclear Data information is fundamental Realisation that the needs of nuclear data -for fusion are different from those of fission meant that it was appropriate to produce -a specific data library to address these needs The Fusion Evaluation Nuclear Data -Library (FENDL) was the response of the IAEA to the need for a data library specifically -designed for fusion applications An initial meeting was held in 1989 and following -the creation and testing of FENDL-1 in 1995 work started on FENDL-2 This work culminated -in the release of the library FENDL-2 containing evaluations judged to be the best -available in February 1997}, - author = {Forrest, R.A. and Capote, R. and Otsuka, N. and Kawano, T. and Koning, A.J. and Kunieda, S. and Sublet, J-Ch. and Watanabe, Y.}, - year = {2012}, - note = {INDC(NDS)--0628 -INIS Reference Number: 44045168}, - pages = {26}, -} - -@book{mccracken_fusion_2013, - address = {Boston}, - title = {Fusion ({Second} {Edition})}, - isbn = {978-0-12-384656-3}, - url = {http://www.gammaexplorer.com/wp-content/uploads/2014/03/Fusion-The-Energy-of-the-Universe.pdf}, - language = {en}, - urldate = {2022-06-08}, - publisher = {Academic Press}, - editor = {McCracken, Garry and Stott, Peter}, + urldate = {2022-06-09}, + journal = {Proceedings of the Physical Society. Section B}, + author = {Lawson, J. D.}, month = jan, - year = {2013}, - doi = {10.1016/B978-0-12-384656-3.00015-5}, - file = {Fusion-The-Energy-of-the-Universe.pdf:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\HH7RHB97\\Fusion-The-Energy-of-the-Universe.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\rdelaporte\\ownCloud\\Zotero\\storage\\XX8YCY6R\\B9780123846563000155.html:text/html}, -} - -@article{webster_fusion_2003, - title = {Fusion: {Power} for the future}, - volume = {38}, - issn = {0031-9120}, - shorttitle = {Fusion}, - url = {https://doi.org/10.1088/0031-9120/38/2/305}, - doi = {10.1088/0031-9120/38/2/305}, - abstract = {There is a growing recognition that we need an alternative to conventional fossil fuels. Shortages of oil and gas have the potential to cause economic and political instability, and burning fossil fuels can cause environmental damage, as well as being the likeliest cause of global warming. Fusion - the process that powers the sun and stars, has the potential to provide large-scale, safe energy production, without adding to global warming and without the long-term radioactive waste associated with conventional fission power stations. More importantly, within the next 20 years large-scale fusion power production is planned to be demonstrated by the multinational experiment ITER, and a proposed `fast track' to fusion envisages a time-scale of roughly 30 years for a prototype power plant PROTO to be built.}, - language = {en}, - number = {2}, - urldate = {2022-06-08}, - journal = {Physics Education}, - author = {Webster, Anthony J.}, - month = mar, - year = {2003}, + year = {1957}, note = {Publisher: IOP Publishing}, - pages = {135--142}, + pages = {6--10}, + file = {IOP Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\NNPK9TD8\\Lawson - 1957 - Some Criteria for a Power Producing Thermonuclear .pdf:application/pdf}, } @misc{delaporte-mathurin_remdelaportemathurinh-transport-materials_2022, @@ -10038,3 +10261,20 @@ @RemDelaporteMathurin in year = {2022}, doi = {10.5281/ZENODO.6627157}, } + +@article{lister_plasma_2006, + title = {Plasma control in {ITER}}, + volume = {26}, + issn = {1941-000X}, + doi = {10.1109/MCS.2006.1615274}, + abstract = {This paper describes the ITER tokamak from the standpoint of operation, with emphasis on the plasma control system. It discusses the plasma operation scenario sequence that is carried out in feedforward control mode, and presents the overall feedback control system, which can be roughly separated into two weakly coupled control loops. Details about each control loop, the magnetic and kinetic controller, are also given.}, + number = {2}, + journal = {IEEE Control Systems Magazine}, + author = {Lister, J.B. and Portone, A. and Gribov, Y.}, + month = apr, + year = {2006}, + note = {Conference Name: IEEE Control Systems Magazine}, + keywords = {Control systems, Magnetic confinement, Materials testing, Neutrons, Niobium-tin, Plasma confinement, Plasma devices, Superconducting coils, Superconducting magnets, Tokamaks}, + pages = {79--91}, + file = {IEEE Xplore Full Text PDF:D\:\\Logiciels\\data_zotero\\storage\\FX3DQIL5\\Lister et al. - 2006 - Plasma control in ITER.pdf:application/pdf}, +} diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index 3f7e79b..a1fcbc1 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -193,12 +193,70 @@ \subsection{Influence of interface condition} \input{chapters/chapter3/monoblocks/interface_conditions} \subsection{Influence of cycling} + +In ITER, the plasma operation will not be continuous. +Instead, pulses of \SI{600}{s} will be shot \sidecite{lister_plasma_2006} with a ramp-up of \SI{100}{s}, a plateau during \SI{400}{s}, a ramp-down of \SI{100}{s} and \SI{1000}{s} of dwell time between pulses (see \reffig{plasma cycle}). +Simulating these transient cycles would require stepsizes of $\approx \SI{10}{s}$ in order to capture the ramp-up and ramp-down phases. +Simulating one cycle would therefore require more than 60 steps (excluding the resting phase). + +On the other hand, FESTIM has an adaptive stepsize feature allowing the stepsize to increase (resp. decrease) when steps are solved in less (resp. more) than 5 Newton iterations. +Therefore, if a continuous plasma exposure was simulated, the adaptive stepsize would allow the stepsize to increase up to thousands of seconds, reducing a lot the simulation time. + +To verify the validity of this approximation, 1D simulations were run with plasma cycles or continuous exposure. +For the cycled simulation, both the heat flux $\varphi_\mathrm{heat}$ and the particle flux $\varphi_\mathrm{imp}$ were varied from zero during the resting phases to their nominal values during the plateau phase (see \reffig{plasma cycle}). + +Two cases were run: +\begin{itemize} + \item High flux: $\varphi_\mathrm{heat} = \SI{13}{MW.m^{-2}}$ and $\varphi_\mathrm{imp} = \SI{1.6e22}{m^{-2}.s^{-1}}$ + \item Low flux: $\varphi_\mathrm{heat} = \SI{5}{MW.m^{-2}}$ and $\varphi_\mathrm{imp} = \SI{5.0e21}{m^{-2}.s^{-1}}$ +\end{itemize} + +In the high flux case, the surface temperature is about $\SI{1400}{K}$ during the plateau whereas it is only $\approx \SI{500}{K}$ for the low flux case. +The evolution of the inventory for both cases was calculated with or without cycling (see \reffig{monoblock inventory cycling}). +To be able to compare the cases, the inventory is shown as a function of the fluence: +\begin{equation} + \mathrm{fluence}(t) = \int_0^t \varphi_\mathrm{imp}(t) \, dt +\end{equation} + + +\begin{figure} + \centering + \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/cycle.pdf} + \caption{} + \labfig{plasma cycle} +\end{figure} + \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/comparison_inventory_cycling.pdf} \caption{} + \labfig{monoblock inventory cycling} \end{figure} +For the continuous cases, the inventory evolves as a power law of the fluence (straight line on a log-log scale). +For the cycled simulations, spikes appear periodically (between every cycle). +These spikes correspond to ramp-down and ramp-ups during the cycles. +During the ramp-down, as the temperature decreases, the traps filling ratio increases, which results in an increase in the inventory. +During the resting phase (not shown on \reffig{monoblock inventory cycling} since the flux is null), the inventory is kept constant. +During the ramp-up, the temperature increases again and the hydrogen trapped close to the plasma-facing surface is desorbed and diffuses either back to the plasma, or deeper into the bulk. +Finally, during the plateau phase, the inventory increases as a power law of the fluence. + +These kinetics are observed for both the low flux and high flux cases. +However, in the low flux case, the height of the spikes is greatly reduced. +This is explained by the lower temperature difference between the resting phase and the plateau phase. + +In both cases, the evolution trends are the same with or without cycling and the inventory evolution during the plateau phases nearly match the continuous case. +These results are consistent with the one observed in \sidecite{hodille_modelling_2021} with other trapping parameters. +For a monoblock where the flux is even lower and the temperature difference is almost zero, no spikes will appear, and the cycled and continuous cases will match. + +Moreover, the "height" of these spikes is constant. +This means that, after more cycles, these spikes will become negligible compared to the bulk inventory. +For the high flux case, the inventory spike will be negligible (10\% of the total inventory) after approximately 4000 cycles. +For the low flux case, it is negligble after only 1150 cycles. + +This therefore validates the continuous exposure simplification. + + \section{Monoblock behaviour law} \label{influence of exposure conditions} \input{chapters/chapter3/monoblocks/parametric_study} diff --git a/scripts/plot_cycle.py b/scripts/plot_cycle.py new file mode 100644 index 0000000..2b6a0da --- /dev/null +++ b/scripts/plot_cycle.py @@ -0,0 +1,24 @@ +import matplotlib.pyplot as plt +import matplotx + +t = [0, 100, 500, 600, 1600] +flux = [0, 1, 1, 0, 0] + +plt.figure(figsize=(8, 3)) + +plt.plot(t, flux) + +plt.vlines(t[1:-1], ymin=0, ymax=1, color="tab:grey", linestyles="dashed") +plt.annotate("Ramp-up", (50, 1.05), ha="center") +plt.annotate("Plateau", (300, 1.05), ha="center") +plt.annotate("Ramp-down", (550, 1.05), ha="center") +plt.annotate("Rest", (1000, 1.05), ha="center") +plt.xticks(t) +plt.yticks([]) +plt.xlabel("Cycle time (s)") +matplotx.ylabel_top(r"$\varphi_\mathrm{heat}$" + "\n" + r"$\varphi_\mathrm{imp}$") +plt.gca().yaxis.label.set_size(13) +plt.gca().spines.right.set_visible(False) +plt.gca().spines.top.set_visible(False) +plt.tight_layout() +plt.show() From 789fdb35062f53e708b9186f366e797e9cb879eb Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Wed, 15 Jun 2022 10:46:17 +0200 Subject: [PATCH 11/22] added captions --- chapters/chapter3/monoblocks.tex | 6 +++--- 1 file changed, 3 insertions(+), 3 deletions(-) diff --git a/chapters/chapter3/monoblocks.tex b/chapters/chapter3/monoblocks.tex index a1fcbc1..894666a 100644 --- a/chapters/chapter3/monoblocks.tex +++ b/chapters/chapter3/monoblocks.tex @@ -222,18 +222,18 @@ \subsection{Influence of cycling} \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/cycle.pdf} - \caption{} + \caption{ITER plasma cycle. Evolution of heat flux and implanted particle flux.} \labfig{plasma cycle} \end{figure} \begin{figure} \centering \includegraphics[width=\linewidth]{Figures/Chapter3/monoblocks/comparison_inventory_cycling.pdf} - \caption{} + \caption{Evolution of the monoblock inventory as a function of the implanted fluence for cycled (solid) and continuous (dashed) exposure.} \labfig{monoblock inventory cycling} \end{figure} -For the continuous cases, the inventory evolves as a power law of the fluence (straight line on a log-log scale). +For the continuous cases, the inventory evolves as a power law of the fluence. For the cycled simulations, spikes appear periodically (between every cycle). These spikes correspond to ramp-down and ramp-ups during the cycles. During the ramp-down, as the temperature decreases, the traps filling ratio increases, which results in an increase in the inventory. 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When $t \gg \tau$, $c_\mathrm{max}(t) \approx \frac{R_p \varphi_\mathrm{imp}}{D} + \sqrt{\frac{\varphi_\mathrm{imp}}{K_r}}$ -\subsection{Interface condition: conservation of chemical potential} +\subsection{Interface condition: conservation of chemical potential}\refsec{conservation of chemical potential} % According to Krom \textit{et al} \sidecite{krom_hydrogen_2000}, since the solubility of hydrogen atoms in solids is low, the chemical potential of solute hydrogen $\mu$ is expressed by: % \begin{equation} % \mu = \mu_0 + RT \ln\left( \frac{c_\mathrm{m}}{N_L}\right) From 4f5e0a0d7ed4d09f68b86a552b53e1c8ba624a79 Mon Sep 17 00:00:00 2001 From: RemDelaporteMathurin Date: Wed, 15 Jun 2022 14:04:23 +0200 Subject: [PATCH 14/22] finished writing influence of interface conditions --- .../difference_w_wo_chemical_pot.pdf | Bin 0 -> 31602 bytes .../iter case/mobile_chemical_pot.pdf | Bin 0 -> 2111543 bytes .../iter case/mobile_concentration.pdf | Bin 0 -> 178867 bytes .../iter 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case/mobile_concentration.pdf delete mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/retention_c.pdf create mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/retention_chemical_pot.pdf create mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/retention_concentration.pdf delete mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/retention_mu.pdf delete mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/solute_c.pdf delete mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/solute_mu.pdf delete mode 100644 Figures/Chapter3/monoblocks/interface_condition/iter case/temperature_field_2d.pdf create mode 100644 Figures/Chapter3/monoblocks/interface_condition/retention_chemical_pot_short_exposure.pdf create mode 100644 Figures/Chapter3/monoblocks/interface_condition/retention_concentration_short_exposure.pdf diff --git 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