Deuterium retention and trapping in tungsten plasma sprayed layers after low energy plasma irradiation was investigated by means of thermal desorption technique. Plasma irradiation at low temperatures (<650 K) showed the retention and trapping similar to polycrystalline tungsten material. On the other hand, irradiation at high temperatures (>650 K) showed significant increase of the retention in the plasma sprayed layers contrary to the polycrystalline material. Thermal desorption spectra showed extremely high temperatures of the peak positions which are non-typical for the tungsten materials. The possible reasons for such high deuterium retention in the plasma sprayed layers after irradiation at high temperatures and the possible trapping ...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
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...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Deuterium retention studies are presented for nanostructured tungsten films exposed to high-flux deu...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
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...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Deuterium retention studies are presented for nanostructured tungsten films exposed to high-flux deu...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-fl...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...