Deuterium (D) plasma driven permeation (PDP) experiments for tungsten (W) samples were conducted by a linear radio frequency (RF) plasma device. In the PDP experiment, the W sample surface is perpendicular to the grain elongation direction. The D ion flux is in the order of 1021 m−2 s−1 determined by a double Langmuir probe. The results show that bias had a limited effect on the D plasma driven permeation behavior. The D recombination coefficient on W surface is obtained at the temperature ranging from 740 K to 1031 K. The experimentally measured recombination coefficient for a pristine W surface is lower than that for a clean W surface. The effect of recombination coefficient on the D permeation and retention behaviors in W are studied by ...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
A method to measure deuterium permeation through tungsten near room temperature under plasma loading...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
The effect of periodic irradiation on Deuterium (D) retention and blistering in Tungsten (W) was inv...
Hydrogen isotopes plasma-driven permeation (PDP) through F82H coated with two different types of tun...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
A method to measure deuterium permeation through tungsten near room temperature under plasma loading...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D-2 (+) and 10 keV C+ w...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
The effect of periodic irradiation on Deuterium (D) retention and blistering in Tungsten (W) was inv...
Hydrogen isotopes plasma-driven permeation (PDP) through F82H coated with two different types of tun...
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was stud...
Polycrystalline, annealed tungsten targets were bombarded with 12.3MeV W4+ ions to various damage le...
Surface morphology and deuterium retention in tungsten exposed at surface temperature of  5...