International audienceThe possible synergistic effect and mutual influence of the defect production by W-ion damaging and presence of hydrogen isotopes in the crystal lattice of tungsten is studied. For this purpose we perform modelling of the experimental data where samples were in one case sequentially damaged by W ions followed by D-atom exposure and in the other case simultaneously damaged by W ions and exposed to D atoms. Modeling is performed by the MHIMS (migration of hydrogen isotopes in materials) code in which a model of trap creation due to W-ion irradiation during the D-atom exposures is implemented. With the help of the surface model and the experimental data the migration barrier from the surface to the bulk is determined as a...
Tungsten is a primary candidate for plasma facing materials for future fusion devices. An important ...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
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...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
International audienceSimulations of deuterium (D) atom exposure in self-damaged polycrystalline tun...
The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) du...
International audienceIn this work, a kinetic model is presented to describe hydrogen absorption and...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Characteristics of irradiation-induced hydrogen trapping in tungsten were investigated by observing ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Tungsten is a primary candidate for plasma facing materials for future fusion devices. An important ...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
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...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
International audienceSimulations of deuterium (D) atom exposure in self-damaged polycrystalline tun...
The effect of deuterium (D) presence on the amount of displacement damage created in tungsten (W) du...
International audienceIn this work, a kinetic model is presented to describe hydrogen absorption and...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Characteristics of irradiation-induced hydrogen trapping in tungsten were investigated by observing ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Tungsten is a primary candidate for plasma facing materials for future fusion devices. An important ...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...