7.プラズマ対向材料の***ージョン特性(<小特集>熱粒子制御のためのプラズマ対向壁工学)

概要

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The lifetime of plasma facing components can be determined by measurement of the erosion of plasma facing materials. This paper describes the erosion characteristics of candidate plasma facing materials, such as CFC and W, for use in ITER. In ITER, chemical sputtering with hydrogen isotopes becomes dominant for the erosion mechanism of CFC under normal operation. Preferential sputtering of the matrix part of CFC also takes place. To reduce the chemical sputtering, doping of B_4C is effective. In the case of such off-normal events as disruption, erosion by thermal shock becomes dominant for the erosion mechanism of W. Disruption erosion is enhanced both with increase of irradiation temperature and decrease of thermal conductivity.
社団法人プラズマ・核融合学会の論文
1997-06-25