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HiRadMat (High Irradiation to Materials) is a new facility under construction at CERN designed to provide highintensity pulsed beams to an irradiation area where material samples as well as accelerator component assemblies can be tested. The facility uses ...
Tungsten plate was exposed in the TEXTOR tokamak during nitrogen-assisted discharges. In order to determine material mixing on tungsten, the plate was examined ex situ with ion beam analysis techniques including time-of-flight heavy ion elastic recoil dete ...
Carbide-based catalysts, MoC and WC embedded in ordered nanomesoporous carbon were developed for the redn. of triiodide in DSSCs. CV, EIS, Tafel polarization, and photocurrent/voltage tests confirm the excellent catalytic activity of the synthesized carbid ...
The corrosion and tribocorrosion of tungsten in 0.01 M H2SO4, without and with the presence of lactic acid and phosphoric acid as chelating agents was studied here. ...
In the current research, pressureless melt infiltration (PM!) was applied to study the effect of different processing conditions on the final properties of Al/SiC composites, fabricated through the infiltration of aluminum melt into SiC particulates porous ...
Fragmented solid targets made of either fluidised tungsten powder or static pebble bed of tungsten spheres, have been long proposed and are being studied as an alternative configuration towards high-power (>1 MW of beam power) target systems, suitable for ...
The GFR (Gas cooled Fast Reactor) combines the advantages of a fast neutron spectrum with those of high temperatures. Given the high core outlet temperatures exceeding 800 C, it is clear that conventional metallic core structures and fuel cladding will be ...
Results are presented for heat loads at the TCV outer divertor target during ELMing H-mode using a fast IR camera. Benefitting from a recent surface cleaning of the entire first wall graphite armour, a comparison of the transient thermal response of freshl ...
The main objectives of the JET ITER-like Wall Project are to provide a beryllium main wall and tungsten divertor with at least a 4 year lifetime to allow full evaluation of the materials and related plasma scenarios for ITER. Tungsten coatings will be used ...
Results are presented for heat loads at the TCV outer divertor target during ELMing H-mode using a fast IR camera. Benefitting from a recent surface cleaning of the entire first wall graphite armour, a comparison of the transient thermal response of freshl ...
