AbstractThermal 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 tra...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
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 irradi...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
The role of lattice defects on deuterium retention in tungsten was investigated by using specially p...
International audienceSelf-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simu...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
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...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
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 irradi...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
Deuterium (D) interaction with vacancies in tungsten (W) was studied using thermal desorption spectr...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tu...
AbstractEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavi...
The role of lattice defects on deuterium retention in tungsten was investigated by using specially p...
International audienceSelf-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simu...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The influence of the presence of deuterium on displacement damage in tungsten is studied by implanti...
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...
Tungsten has been proposed for first wall material in thermonuclear reactors, where its behaviour in...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...