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 interaction processes between the burning plasma and the first wall in a fusion reactor
are diverse: the first wall will be exposed to extreme thermal loads of up to several tens of …

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 …

Plasma wall interaction (PWI) is important for the material choice in ITER and for the plasma
scenarios compatible with material constraints. In this paper, different aspects of the PWI are …

The heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …

Component development for operation in a large-scale fusion device requires thorough
testing and qualification for the intended operational conditions. In particular environments …

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 …

ME Fenstermacher, TE Evans, TH Osborne, MJ Schaffer, MP Aldan, JS deGrassie, P. Gohil,
I. Joseph, RA Moyer, PB Snyder, RJ Groebner, M. Jakubowski, AW Leonard, O. Schmitz, the …

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 …

Large edge-localized mode (ELM) control techniques must be developed to help ensure the
success of burning and ignited fusion plasma devices such as tokamaks and stellarators. In …