We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten exposed to high-flux deuterium plasmas. The retention saturates at a W 4+ fluence of about 3 × 10 17  m −2 and is strongly reduced for the present high surface temperatures of 800–1200 K as compared with previous experiments at 470–525 K. Combination of nuclear reaction analysis (NRA), thermal desorption spectroscopy and positron annihilation Doppler broadening (PADB) was used to investigate the reduction in deuterium retention. The NRA showed a strong reduction of retention at the surface at high surface temperatures. The PADB measurements suggest that during plasma exposure defects are mobile and c...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
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...
Systematic study of deuterium irradiation effects on tungsten was done under ITER – relevant high pa...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
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...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Two sets of identical tungsten (W) targets are irradiated at 300 K with 12.3 MeV W4+ ions to peak da...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
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...
Systematic study of deuterium irradiation effects on tungsten was done under ITER – relevant high pa...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W4+ ions to various damage l...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
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...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Two sets of identical tungsten (W) targets are irradiated at 300 K with 12.3 MeV W4+ ions to peak da...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...