Tungsten (W) and molybdenum (Mo) targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (ne ~ 1020 m−3, Te ~ 2 eV) in the linear plasma device Pilot-PSI. The peak surface temperatures of the targets are ~1600 K for W and ~1100 K for Mo. The surface temperatures and plasma flux densities decrease radially towards the edges of the target due to the Gaussian distribution of electron density (ne) and temperature (Te) in the plasma column. A 2D spatial scan of the W and Mo targets using nuclear reaction analysis (NRA) shows D retention is strongly influenced by surface temperature in the range 800–1600 K and this dependence dominates over any plasma flux dependence. NRA and thermal desorption spectr...
At FOM Rijnhuizen, linear plasma generators are used to investigate plasma-material interactions und...
Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads fro...
To understand the fuel retention mechanism correlation of surface chemical states and hydrogen isoto...
Tungsten (W) and molybdenum (Mo) targets are exposed to the plasma conditions expected at the strike...
Tungsten (W) and molybdenum (Mo) targets are exposed to the plasma conditions expected at the strike...
Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITE...
Refractory materials are being considered potential candidates to build the first wall of the fusion...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The retention of deuterium (D) fuel in the Alcator C-Mod tokamak is studied using a new \u27static\u...
In order to study the diffusion, surface recombination and trapping of hydrogen isotopes in tungsten...
At FOM Rijnhuizen, linear plasma generators are used to investigate plasma-material interactions und...
At FOM Rijnhuizen, linear plasma generators are used to investigate plasma-material interactions und...
Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads fro...
To understand the fuel retention mechanism correlation of surface chemical states and hydrogen isoto...
Tungsten (W) and molybdenum (Mo) targets are exposed to the plasma conditions expected at the strike...
Tungsten (W) and molybdenum (Mo) targets are exposed to the plasma conditions expected at the strike...
Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITE...
Refractory materials are being considered potential candidates to build the first wall of the fusion...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Systematic study of deuterium irradiation effects on tungsten was done under ITER - relevant high pa...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
The retention of deuterium (D) fuel in the Alcator C-Mod tokamak is studied using a new \u27static\u...
In order to study the diffusion, surface recombination and trapping of hydrogen isotopes in tungsten...
At FOM Rijnhuizen, linear plasma generators are used to investigate plasma-material interactions und...
At FOM Rijnhuizen, linear plasma generators are used to investigate plasma-material interactions und...
Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads fro...
To understand the fuel retention mechanism correlation of surface chemical states and hydrogen isoto...