Abstract
Erosion of ITER plasma-facing components (PFCs) is analysed with a strike-point carbon divertor target and metallic walls (Be in the main chamber, and W divertor baffles), for a ‘semi-detached’ edge plasma regime, with Type I ELMs and off-normal events (e.g. disruptions). This paper builds on earlier studies [J. Nucl. Mater. 290–293 (2001) 260], refines the assessment of erosion during full DT operation with long cumulative burn time, and discusses erosion effects expected during early phases of operation with H and DD plasmas. The present analysis should be viewed as more reliable for indicating trends, rather than providing firm quantitative predictions. Outstanding issues are identified and recommendations are made for further urgent R&D.
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