7. プラズマ対向材料におけるトリチウム研究(<小特集> プラズマ閉じ込め性能向上のためのプラズマ対向機器(PFC)開発およびプラズマ表面相互作用(PSI)研究の現状)

概要

論文の詳細を見る
Current status of tritium retention and permeation studies for plasma facing materials is briefly reviewed. Generally amounts of tritium retained in and permeated through plasma facing materials by plasma-material interactions are much larger than those by gas-material interactions. To estimate the tritium inventory and permeation rates in plasma facing components is essential for fusion safety issues. However, precise estimations have not been successful because of discrepancies among the data like diffusivity, solubility, recombination factor, permeability, etc. which caused mainly by characterization of samples, impurities on surface, etc. The studies in the past and the activities in the ITER program are presented.
社団法人プラズマ・核融合学会の論文
1995-05-25