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 …

An overview of the present status of research toward the final design of the ITER disruption
mitigation system (DMS) is given. The ITER DMS is based on massive injection of impurities …

The choice of materials for the future nuclear fusion reactors is a crucial issue. In the fusion
reactors, the combination of very high temperatures, high radiation levels, intense …

For several reasons the challenge to keep the loads to the first wall within engineering limits
is substantially higher in DEMO compared to ITER. Therefore the pre-conceptual design …

Recent research in scrape-off layer (SOL) and divertor physics is reviewed; new and existing
data from a variety of experiments have been used to make cross-experiment comparisons …

A new experimental setup has been developed for edge localized mode (ELM) simulation
experiments with relevant steady-state plasma conditions and transient heat/particle source …

The development of small edge localized mode (ELM) scenarios is important in order to
reduce the strain on plasma facing components. One such scenario can be found at high …

This paper is concerned with investigation of an erosion of the ITER-like divertor castellated
targets of pure tungsten, lanthanum tungsten and CFC under plasma heat loads expected …

The behaviour of the recovery of the electron temperature and density during individual ELM
(edge localized mode) cycles has been examined closely for a series of type I ELMy H-mode …

Cracking thresholds and crack patterns in tungsten targets after repetitive ITER-like edge
localized mode (ELM) pulses have been studied in recent simulation experiments by laser …