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 …

Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …

Edge-localized-modes (ELMs) are a ubiquitous feature of H-mode in tokamaks. When
gradients in the H-mode transport barrier grow to exceed the MHD stability limit the ELM …

The characterization of plasma bursts produced after the pinch phase in a plasma focus of
hundreds of joules, using pulsed optical refractive techniques, is presented. A pulsed Nd …

Recent results of ELM-simulation experiments with quasi-stationary plasma accelerators
(QSPAs) Kh-50 (Kharkov, Ukraine) and QSPA-T (Troitsk, Russia) as well as experiments in …

Cracking thresholds and crack patterns (major-and micro-) as well as residual stresses in
tungsten targets after repetitive ITER ELM-like plasma pulses have been studied in recent …

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 …

A table top plasma focus device operating at hundreds of joules was used to simulate an
equivalent damage factor than the obtained on the divertor in tokamak experiments. Using …

Experimental simulations of ITER transient events with surface heat load parameters
relevant to edge-localized-mode (ELM) impacts and disruptions have been performed with a …

In recent tokamak simulation experiments with the QSPA Kh-50 facility several mechanisms
of dust generation from tungsten surfaces under ITER ELM-like energy loads have been …