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

H. Ushida, Kazunari Katayama, Hideaki Matsuura, R. Yamamoto, Satoshi Fukada, M. Goto, S. Nakagawa

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)524-528
Number of pages5
JournalNuclear Materials and Energy
Volume9
DOIs
Publication statusPublished - Dec 1 2016

Fingerprint

high temperature gas cooled reactors
High temperature gas reactors
Tritium
fusion reactors
Fusion reactors
tritium
Permeation
Hydrogen
Carbon
carbon
hydrogen
reactors
coatings
production engineering
Reactor operation
Coatings
Graphite
high resistance
Ceramic materials
diffusivity

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science (miscellaneous)
  • Nuclear Energy and Engineering

Cite this

Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors. / Ushida, H.; Katayama, Kazunari; Matsuura, Hideaki; Yamamoto, R.; Fukada, Satoshi; Goto, M.; Nakagawa, S.

In: Nuclear Materials and Energy, Vol. 9, 01.12.2016, p. 524-528.

Research output: Contribution to journalArticle

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AU - Fukada, Satoshi

AU - Goto, M.

AU - Nakagawa, S.

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