トリチウムの取扱い技術-主としてわが国における研究を中心として
1984 年 51 巻 3 号 p. 149-161
詳細
1984 年 51 巻 3 号 p. 149-161
After the tritium inventories of many proposed or exixting fusion test reactors have been surveyed, the behaviour of tritium in fusion environment and the proposed containment systems, in relation to the fusion reactor safety, are stressed. The values of permeabilities through stainless steel, niobium, poly-tetrafluoroethylene, polyethylene, polycarbonate and stainless steel covered with polycarbonate, which are obtained by japanese researcher, are summarized. Clearly the obtained results described here could be applicable to fusion reactor systems.
