A recently developed numerical model, based on the dislocation-driven nucleation of gas bubbles, is used to analyse experimental results on deuterium retention in tungsten under ITER relevant plasma exposure conditions. Focus is placed on understanding the relation between exposure temperature and flux on primary features of thermal desorption spectra: peak positions and intensities of the desorption flux. The model allows one to relate the peak positions with the size of plasma induced deuterium bubbles and envisage exposure conditions (temperature and flux) for their formation. Based on the performed analysis, dedicated experimental conditions to validate the model are proposed
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
A recently developed numerical model, based on the dislocation-driven nucleation of gas bubbles, is ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
In order to study the diffusion, surface recombination and trapping of hydrogen isotopes in tungsten...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The accumulation of deuterium implanted in tungsten is simulated within the framework of kinetic dif...
Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at ...
Deuterium retention and trapping in tungsten plasma sprayed layers after low energy plasma irradiati...
Tungsten is a primary candidate for plasma facing materials for future fusion devices. An important ...
Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITE...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...
A recently developed numerical model, based on the dislocation-driven nucleation of gas bubbles, is ...
Tungsten targets are irradiated with 12.3 MeV W4+ ions to damage levels up to 2.0 displacements per ...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
In order to study the diffusion, surface recombination and trapping of hydrogen isotopes in tungsten...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The accumulation of deuterium implanted in tungsten is simulated within the framework of kinetic dif...
Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at ...
Deuterium retention and trapping in tungsten plasma sprayed layers after low energy plasma irradiati...
Tungsten is a primary candidate for plasma facing materials for future fusion devices. An important ...
Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITE...
The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy t...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
Surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low ...