Effect of temperature distribution on tritium permeation rate to cooling water in JA DEMO condition

Kazunari Katayama, Youji Someya, Takumi Chikada, Kenji Tobita, Hirofumi Nakamura, Yuji Hatano, Ryoji Hiwatari, Yoshiteru Sakamoto, Akito Ipponsugi, Makoto Oya

研究成果: Contribution to journalArticle査読

抄録

The estimation of tritium permeation rate through the plasma facing wall into coolant is required to discuss tritium balance in a D-T fusion plant, to design tritium recovery system and to perform safety assessments. In this work, tritium permeation rates in the blanket first wall and the divertor were estimated by numerical analysis for simplified multi-layer structures with considering the temperature distribution in recent JA DEMO condition. The permeation rate in the blanket first wall, which was a double layer consisting of tungsten and F82H, was estimated to be 0.69 g/day. The permeation rate in the divertor, which was a triple layer consisting of tungsten, copper and copper alloy or F82H, was estimated to be 0.013 g/day. When the permeation rate in tritium breeding region in the blanket can be reduced by three orders of magnitude due to a permeation barrier, total tritium permeation rate in the blanket and the divertor was estimated to be 0.71 g/day.

本文言語英語
論文番号112576
ジャーナルFusion Engineering and Design
169
DOI
出版ステータス出版済み - 8 2021

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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