Description: Several methods for reducing impurity contamination in near-term tokamak reactors by modifying the first-wall surface with a low-Z or low-sputter material are examined. A review of the sputtering data and an assessment of the technological feasibility of various wall modification schemes are presented. The power performance of a near-term tokamak reactor is simulated for various first-wall surface materials, with and without a divertor, in order to evaluate the likely effect of plasma contamination associated with these surface materials.
Date: October 1, 1976
Creator: Stacey, W. M. Jr.; Smith, D. L. & Brooks, J. N.
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Partner: UNT Libraries Government Documents Department