Erosion of ITER plasma-facing components (PFCs) is analysed with a strike-point carbon divertor target and,, plasma 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 is 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 RD. (C) 2002 Elsevier Science B.V. All rights reserved.
机构:
ITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, FranceITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, France
Pshenov, A. A.
Bonnin, X.
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ITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, FranceITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, France
Bonnin, X.
Pitts, R. A.
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ITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, FranceITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, France