Design of gaseous tritium recovery system applying commercially available membrane-type dehumidifier

Yamato Asakura, Masahiro Tanaka, Tatsuhiko Uda, Hideki Ogawa, Shigeyuki Takami, Yasuhisa Oya, Kenji Okuno, Satoshi Fukada

研究成果: Contribution to journalArticle査読

抄録

In order to realize the planned deuterium plasma experiments using the large helical device (LHD), the National Institute for Fusion Science (NIFS) is planning to install a system for tritium recovery from exhaust gas. While adopting typical tritium recovery systems, NIFS has also made plans for the development of a compact reduced-waste recovery system by applying a membrane-type dehumidifier. The applicability of a commercially available membrane dehumidifier has been evaluated experimentally, with the results indicating that such a membrane is feasible for practical application. Based on performance test results, the optimum specifications of the membrane dehumidifier are evaluated quantitatively and an actual tritium recovery system for the LHD has been designed.

本文言語英語
ページ(範囲)641-647
ページ数7
ジャーナルjournal of nuclear science and technology
46
6
DOI
出版ステータス出版済み - 6 2009

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

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