作者: G. Federici , H. Wuerz , G. Janeschitz , R. Tivey
DOI: 10.1016/S0920-3796(02)00298-3
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摘要: 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, W baffles), for ‘semi-detached’ edge plasma regime, Type I ELMs off-normal events (e.g. disruptions). This paper builds on earlier studies [J. Nucl. Mater. 290–293 (2001) 260], refines assessment erosion during full DT operation long cumulative burn time, discusses effects expected early phases H DD plasmas. The present analysis should be viewed as more reliable indicating trends, rather than providing firm quantitative predictions. Outstanding issues are identified recommendations made further urgent R&D.