Retention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa with sample temperatures between 300K and 1200K. At a D plasma ion fluence of 1024/m2 on samples damaged to 0.2dpa at 300K, the retained D retention inventory is 4.6 ×1020D/m2, about ∼5.5 times higher than in undamaged samples. The retained inventory drops to 9 ×1019D/m2 for samples damaged to 0.2dpa at 1000K, consistent with onset of vacancy annealing at a rate sufficient to overcome the elevated rate of ion beam damage; at a damage temperature of 1200K retention is nearly equal to values seen in undamaged materials. A nano-scale technique provides thermal conductivity measurements from the Cu-ion beam displacement damaged region. We find the t...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
Nuclear fusion plasma-facing materials (PFM) will suffer from irradiation, leading to significant ch...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Tungsten is a promising candidate material for plasma-facing armour components in future fusion reac...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
Nuclear fusion plasma-facing materials (PFM) will suffer from irradiation, leading to significant ch...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Tungsten is a promising candidate material for plasma-facing armour components in future fusion reac...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
Nuclear fusion plasma-facing materials (PFM) will suffer from irradiation, leading to significant ch...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...