The retention of deuterium (D) and helium (He) is studied in pure tungsten after high flux mono-plasma exposure. The recrystallized and plastically deformed tungsten samples are studied to clarify the impact of the material microstructure, in particular dislocation density, on the trapping and release of D and He. Thermal Desorption Spectroscopy (TDS) measurements are performed to reveal the release stages and quantify the retention. Preliminary transmission electron microscopy study was applied to clarify the microstructural modifications induced by the plasma exposure to support the discussion and conclusions. It has been demonstrated that plastic deformation causes considerable suppression of He release within the explored limit of the T...
Deuterium (D) retention and surface modifications of hot-rolled polycrystalline tungsten (W) exposed...
Tungsten samples are exposed to 3He plasma to quantify their helium retention behavior. The retentio...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
The retention of deuterium (D) and helium (He) is studied in pure tungsten after high flux mono-plas...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Recent experimental results on tungsten surface morphology, especially nano-structure (fuzz), induce...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Surface morphology and hydrogen isotope retention of W specimen melted with vertical displacement ev...
Deuterium (D) retention and surface modifications of hot-rolled polycrystalline tungsten (W) exposed...
Tungsten samples are exposed to 3He plasma to quantify their helium retention behavior. The retentio...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...
The retention of deuterium (D) and helium (He) is studied in pure tungsten after high flux mono-plas...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
The effect of severe plastic deformation on the deuterium retention in tungsten exposed to high-flux...
Recent experimental results on tungsten surface morphology, especially nano-structure (fuzz), induce...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets...
The influence of surface temperature, particle flux density and material microstructure on the surfa...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
The ITER tokamak is the next step by the international fusion community towards nuclear fusion power...
Surface morphology and hydrogen isotope retention of W specimen melted with vertical displacement ev...
Deuterium (D) retention and surface modifications of hot-rolled polycrystalline tungsten (W) exposed...
Tungsten samples are exposed to 3He plasma to quantify their helium retention behavior. The retentio...
Experimental results from the literature on the evolution of deuterium retention in displacement-dam...