International audienceSimulations 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...
Hydrogen isotopes are retained in plasma-facing fusion materials, triggering hydrogen embrittlement ...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
In this work, we focus on understanding hydrogen isotope retention in plasma-facing materials in fus...
International audienceSimulations of deuterium (D) atom exposure in self-damaged polycrystalline tun...
International audienceThe possible synergistic effect and mutual influence of the defect production ...
The possible mutual influence and synergistic effect between defect production and the presence of h...
International audienceIn this work, a kinetic model is presented to describe hydrogen absorption and...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) du...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
Hydrogen isotopes are retained in plasma-facing fusion materials, triggering hydrogen embrittlement ...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
In this work, we focus on understanding hydrogen isotope retention in plasma-facing materials in fus...
International audienceSimulations of deuterium (D) atom exposure in self-damaged polycrystalline tun...
International audienceThe possible synergistic effect and mutual influence of the defect production ...
The possible mutual influence and synergistic effect between defect production and the presence of h...
International audienceIn this work, a kinetic model is presented to describe hydrogen absorption and...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) du...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
Hydrogen isotopes are retained in plasma-facing fusion materials, triggering hydrogen embrittlement ...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
In this work, we focus on understanding hydrogen isotope retention in plasma-facing materials in fus...