Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors

H. Ushida, K. Katayama, H. Matsuura, R. Yamamoto, S. Fukada, M. Goto, S. Nakagawa

研究成果: Contribution to journalArticle査読

2 被引用数 (Scopus)

抄録

Under tritium production method using a high-temperature gas-cooled reactor loaded Li compound, Li compound has to be coated by ceramic materials in order to suppress the spreading of tritium to the whole reactor. Pyrolytic carbon (PyC) is a candidate of the coating material because of its high resistance for gas permeation. In this study, hydrogen permeation experiments using a PyC-coated isotropic graphite tube were conducted and hydrogen diffusivity, solubility and permeability were evaluated. Tritium permeation behavior through PyC-coated Li compound particles was simulated by using obtained data. Hydrogen permeation flux through PyC in a steady state is proportional to the hydrogen pressure and is larger than that through Al2O3 which is also candidate coating material. However, total tritium leak within the supposed reactor operation period through the PyC-coated Li compound particles is lower than that through the Al2O3-coated ones because the hydrogen absorption capacity in PyC is considerably larger than that in Al2O3.

本文言語英語
ページ(範囲)524-528
ページ数5
ジャーナルNuclear Materials and Energy
9
DOI
出版ステータス出版済み - 12 1 2016

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(その他)
  • 原子力エネルギーおよび原子力工学

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