Chemical form of released tritium from solid breeder materials under the various purge gas conditions

T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, T. Tanifuji, M. Enoeda

研究成果: Contribution to journalArticle査読

24 被引用数 (Scopus)

抄録

Understanding of the release behavior of bred tritium from solid breeder materials is necessary to design tritium recovery system from blanket of a fusion reactor because permeation loss of bred tritium in the piping system or type of tritium recovery system depends on the tritium release behavior. It has been reported by the present authors that behavior of tritium release from solid breeder grain is consisted of diffusion in grain, tritium transfer at surface layer and surface reactions on grain surface such as adsorption or isotope exchange reactions. Chemical form of released tritium from Li4SiO4 (from FzK), LiAlO2 (from JAERI), Li2TiO3 (from CEA) and Li2ZrO3 (from MAPI) under various purge gas condition is discussed in this study by using the data obtained from the out-of-pile tritium release experiment in JAEA and fitting results estimated by the tritium release model formed by the present authors. And then the tritium release behavior and chemical form of tritium in the test blanket module with solid breeder under the ITER condition is also discussed based on the estimation obtained using the tritium release model.

本文言語英語
ページ(範囲)2147-2151
ページ数5
ジャーナルFusion Engineering and Design
82
15-24
DOI
出版ステータス出版済み - 10 1 2007

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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