小特集 「核融合炉内外におけるトリチウムの回収技術」
核融合炉内外におけるトリチウムの回収技術 6.LHD 実験における排出気体・液体処理系の研究計画
2002 年 78 巻 12 号 p. 1319-1324
詳細
2002 年 78 巻 12 号 p. 1319-1324
In order to realize deuterium plasma control experiments using the Large Helical Device(LHD), NIFS is planning to install a tritium recovery system for use on exhaust gas and effluent liquid. Besides applying the conventional and proved recovery system, NIFS has made development plans for implementation of a compact and less waste generating recovery system by applying the latest technologies such as tritiated water vapor removal with a membrane type dehumidifier and tritium gas extraction with a proton conducting cell.
