The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ were studied. The D permeability was obtained for un-damaged W at various temperatures. For both D-2 (+) and C+ implanted W, the permeability was clearly reduced. But, for the D-2 (+) implanted W, the permeability was recovered by heating at 1173 K and it was almost consistent with that for un-damaged W. In the case of C+ implanted , the permeability was not recovered even if the sample was heated at 1173 K, indicating that the existence of carbon would prevent the recovery of permeation path in W. In addition, transmission electron microscope (TEM) observation showed the voids were grown by heating at 1173 K and not removed, showing the exist...
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias condit...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had b...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Retention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa wit...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Deuterium (D) plasma driven permeation (PDP) experiments for tungsten (W) samples were conducted by ...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias condit...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had b...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Retention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa wit...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Deuterium (D) plasma driven permeation (PDP) experiments for tungsten (W) samples were conducted by ...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias condit...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...