In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …

The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …

New generations of fusion devices need alternative plasma-facing materials. The currently
approved material composition for the first wall and divertor of the ITER tokamak has a …

The erosion of divertor targets caused by high heat fluxes during transients is a serious
threat to ITER operation, as it is going to be the main factor determining the divertor lifetime …

Boron carbide has been proposed for the neutron protection of equipment in the ITER
diagnostic ports and for reducing the dose to maintenance personnel. The chemical …

The review presents experimental studies of plasma-surface interaction and materials
behavior under plasma loads done in the multiple-mirror trap of the GOL-3 facility. In the …

Experiments on the effect of fast heat loads on the surface of tungsten were carried out on
the BETA facility at the Budker Institute. Tungsten samples were uniformly heated by an …

A novel BETA test facility (Beam of Electrons for materials Test Applications) was developed
at the Budker Institute to study the erosion of materials directly during the impact of intense …

Experimental research on behavior of rolled tungsten plates under intense transient heat
loads generated by a powerful (a total power of up to 7 MW) long-pulse (0.1–0.3 ms) …

Tungsten materials are subjected to severe damage when exposed to transient high heat
loads, and the crack initiation and propagation are observed experimentally based on the …