Evaluation of Erosion and Lifetime of ITER Divertor Candidate Materials and Relevant Data from Recent Experiments in the PISCES-B MOD Facility

Y. Hirooka; J. Won; S. Keller; R. Boivin; M. Khandagle; J. N. Brooks

doi:dx.doi.org/10.13182/FST94-A40213

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Evaluation of Erosion and Lifetime of ITER Divertor Candidate Materials and Relevant Data from Recent Experiments in the PISCES-B MOD Facility

Y. Hirooka, J. Won, S. Keller, R. Boivin, M. Khandagle, J. N. Brooks

Fusion Science and Technology / Volume 26 / Number 3P2 / November 1994 / Pages 540-545

Fusion Material and Plasma-Facing Component / Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 / dx.doi.org/10.13182/FST94-A40213

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Divertor materials erosion and lifetime is a critical issue in designing plasma-facing components (PFCs) for ITER. Currently, three materials are considered as candidates to be used for the divertor target plate, namely, beryllium, carbon and tungsten. In this paper, major issues associated with the use of these candidates are reviewed and relevant data obtained from recent PISCES experiments will be discussed with the main emphasis on the wall lifetime issue.