grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amount of D trapped in the material approaches a saturation level of ${\sim}6\times 10\sp{20}$ D/m$\sp2$ for incident fluence ${\ge}10\sp{23}$ D/m$\sp2,$ independent of ion energy or specimen history. For temperatures between 350 and 550 K, higher retention levels are observed, but these levels depend on ion energy, fluence and implantation history. Fluence dependence measurements at 500 K show no sign of saturation below $3 \times 10\sp{24}$ D/m$\sp2$ and the amount retained appears to be diffusion limited. Experiments with pure W foil related to the effect of ion-induced damage on deuterium retention showed that ion-induced surface modification...
Although neon has been considered for impurity seeding in the ITER tungsten divertor, there have bee...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
We have developed a new theoretical model for deuterium (D) retention in tungsten-based alloys on th...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Although neon has been considered for impurity seeding in the ITER tungsten divertor, there have bee...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
We have developed a new theoretical model for deuterium (D) retention in tungsten-based alloys on th...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Although neon has been considered for impurity seeding in the ITER tungsten divertor, there have bee...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...