J.P. Coad

TL;DR: In this article, the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors are reviewed.

TL;DR: In this article, it was shown that deposition and H-isotope retention in JET is highly asymmetric, with deposition predominantly in the inner divertor, where flaking deposits form on water-cooled louvres shadowed from the plasma.

TL;DR: In this paper, the tritium inventory reached a virtually steady level of about 6 g by the end of the campaign, reaching a high of about 40% of the total input.

TL;DR: A detailed in situ photographic survey of the main chamber and divertor was completed in this article, where the first conclusions regarding erosion, deposition, fuel retention and material transport during divertor and limiter phases have been drawn.

TL;DR: In this paper, a detailed study of hydrogenic isotope recycling and retention in a pumped divertor configuration relevant to ITER is presented, which suggests that ITER may reach its tritium inventory limit in less than 100 pulses.