W R Wampler

TL;DR: In this article, the authors review 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.

TL;DR: In this article, the authors present the results of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as the plasma edge conditions, the surface temperature, the presence of mixed-materials, etc.

TL;DR: In this paper, the authors examined the assumptions underlying tritium retention in materials and, based on assessments of applicable data ranges for each parameter, made projections to ITER for two limiting cases of main chamber fluxes, low (10 23 /s) and high (10 24 /s), as well as for the standard ITER materials of Be first-wall, CFC strike points, W baffle and dome, and all other cases: all-C, all-W divertor and Be first wall.

TL;DR: In this paper, the authors used divertor and midplane material evaluation systems (DiMES and MiMES) in the DIII-D tokamak to address a variety of plasma-material interaction (PMI) issues relevant to ITER.

TL;DR: In this paper, the authors survey factors relevant to material choices in next-step devices, describes advantages and disadvantages of various options, and discusses how their application depends on the specific operational requirements.