In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He+ was approximately one order of magnitude lower than that for un-damaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for un-damaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability ...
Impurity seeding of noble gases is an effective way of decreasing the heat loads onto the divertor t...
Tritium accumulation in nuclear fusion reactor materials is a major concern for practical and safe f...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced int...
The trapping behavior of deuterium and helium in polycrystalline tungsten (PCW) under D+-only, He+-o...
Permeability, diffusivity, and solubility of deuterium in the low-activation martensitic stainless s...
The influence of helium and argon impurities on the deuterium retention in tungsten is investigated ...
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias condit...
To investigate effects of helium irradiation on deuterium retention properties in tungsten, thermal ...
AbstractIn the present work hydrogen isotopes exchange in recrystallized tungsten was investigated a...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
International audienceThe possible synergistic effect and mutual influence of the defect production ...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Impurity seeding of noble gases is an effective way of decreasing the heat loads onto the divertor t...
Tritium accumulation in nuclear fusion reactor materials is a major concern for practical and safe f...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced int...
The trapping behavior of deuterium and helium in polycrystalline tungsten (PCW) under D+-only, He+-o...
Permeability, diffusivity, and solubility of deuterium in the low-activation martensitic stainless s...
The influence of helium and argon impurities on the deuterium retention in tungsten is investigated ...
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias condit...
To investigate effects of helium irradiation on deuterium retention properties in tungsten, thermal ...
AbstractIn the present work hydrogen isotopes exchange in recrystallized tungsten was investigated a...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
International audienceThe possible synergistic effect and mutual influence of the defect production ...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Impurity seeding of noble gases is an effective way of decreasing the heat loads onto the divertor t...
Tritium accumulation in nuclear fusion reactor materials is a major concern for practical and safe f...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...