International audienceWe performed a direct comparison of deuterium retention and release from tungsten in presence or in absence of oxygen impurities. A single crystal of W(110) was used to prepare tungsten with four different surface states: with its native oxide, atomically clean, covered with half a monolayer of oxygen atoms, and covered with three fourths of a monolayer of oxygen atoms. For a D ion fluence of 3 × 10 21 D + m −2 implanted at 300 K, deuterium retention was highest with the native oxide, lowest with three fourths of a monolayer of oxygen atoms at the surface and intermediate for the clean surface. This counterintuitive result is explained by a different localization of deuterium retention in these samples. For tungsten wi...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
International audienceWe performed a direct comparison of deuterium retention and release from tungs...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
International audienceThe time evolution of fuel retention in materials relevant for future fusion r...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
The deposited W layers formed on the W plate by hydrogen plasma sputtering were exposed to deuterium...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
The retention of radioactive tritium in the reactor wall is a safety issue and should be kept to a m...
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...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
International audienceWe performed a direct comparison of deuterium retention and release from tungs...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
International audienceThe time evolution of fuel retention in materials relevant for future fusion r...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
The deposited W layers formed on the W plate by hydrogen plasma sputtering were exposed to deuterium...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
The retention of radioactive tritium in the reactor wall is a safety issue and should be kept to a m...
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...
The hydrogen retention in fusion reactors can be significantly influenced by the presence of plasma ...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...