Thermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed after irradiation with 8 MeV-electrons, 5.0keV-D2+, and 6.0 MeV-Fe3+. The release peak temperatures of the TDS spectra are discussed. Positron annihilation lifetime (PAL) measurements of electron-irradiated tungsten were also performed, showing that single vacancies migrate a sufficient distance to arrive at a sink or meet interstitial-type defects during annealing at 673K. A decrease in the PAL was detected for single vacancies that contain deuterium atoms. The peak temperature of deuterium release from dislocations was lower than that from single vacancies. In samples irradiated with 6.0 MeV-Fe3+, the effect of Fe contamination on deuterium trapping an...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Thermal desorption spectroscopy (TDS) of tungsten implanted with D2 + ions was performed after irrad...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
International audienceSelf-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simu...
The role of lattice defects on deuterium retention in tungsten was investigated by using specially p...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
A positron lifetime component of ~170 ps has been reported for irradiated tungsten (W) in some studi...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Thermal desorption spectroscopy (TDS) of tungsten implanted with D2 + ions was performed after irrad...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
International audienceSelf-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simu...
The role of lattice defects on deuterium retention in tungsten was investigated by using specially p...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
A positron lifetime component of ~170 ps has been reported for irradiated tungsten (W) in some studi...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...