Tritium recovery from liquid blanket systems for fusion reactor

Satoshi Fukada, Y. Edao, K. Katekari, H. Okitsu, Y. Hatachi, M. Okada, K. Tamari

Research output: Contribution to journalArticle

3 Citations (Scopus)

Abstract

Systems to Recover Tritium (T) from Fusion Liquid Blankets of LiPb (Li 17Pb18) and Flibe (Li2BeF4 under safety conditions are discussed based on available data of T transport properties. We recently performed experiments on hydrogen isotopes permeating through LiPb in Kyushu University and introduced them in the present paper. Solubilities, diffusivities and permeabilities of H and D through Li 17Pb83 are determined by means of a transient permeation method. Their isotope effects between H and D in the Li-Pb eutectic alloy are found to be independent of D/H atomic ratio and a function of only temperature. Tritium recovery apparatuses of a liquid-gas counter-current flowing bed or a T permeation window are designed in the liquid blanket system composed of the primary coolant of Flibe or LiPb and the secondary coolant of He or water. Simultaneous transfer of heat and T needs new configuration in order to satisfy the necessary conditions of low T leak and high heat transfer, which make it possible to operate the blanket effectively and safely. Tritium permeation rates through the primary LiPb or Flibe breeder and secondary water or He coolant loops are estimated, which is the most important factor to operate the blanket safely.

Original languageEnglish
Pages (from-to)58-63
Number of pages6
JournalFusion Science and Technology
Volume61
Issue number1 T
DOIs
Publication statusPublished - Jan 1 2012

Fingerprint

Tritium
fusion reactors
blankets
Fusion reactors
tritium
Permeation
Coolants
coolants
recovery
Recovery
Isotopes
Liquids
liquids
Water
permeating
eutectic alloys
Transport properties
Eutectics
hydrogen isotopes
Hydrogen

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Fukada, S., Edao, Y., Katekari, K., Okitsu, H., Hatachi, Y., Okada, M., & Tamari, K. (2012). Tritium recovery from liquid blanket systems for fusion reactor. Fusion Science and Technology, 61(1 T), 58-63. https://doi.org/10.13182/FST12-A13397

Tritium recovery from liquid blanket systems for fusion reactor. / Fukada, Satoshi; Edao, Y.; Katekari, K.; Okitsu, H.; Hatachi, Y.; Okada, M.; Tamari, K.

In: Fusion Science and Technology, Vol. 61, No. 1 T, 01.01.2012, p. 58-63.

Research output: Contribution to journalArticle

Fukada, S, Edao, Y, Katekari, K, Okitsu, H, Hatachi, Y, Okada, M & Tamari, K 2012, 'Tritium recovery from liquid blanket systems for fusion reactor', Fusion Science and Technology, vol. 61, no. 1 T, pp. 58-63. https://doi.org/10.13182/FST12-A13397
Fukada S, Edao Y, Katekari K, Okitsu H, Hatachi Y, Okada M et al. Tritium recovery from liquid blanket systems for fusion reactor. Fusion Science and Technology. 2012 Jan 1;61(1 T):58-63. https://doi.org/10.13182/FST12-A13397
Fukada, Satoshi ; Edao, Y. ; Katekari, K. ; Okitsu, H. ; Hatachi, Y. ; Okada, M. ; Tamari, K. / Tritium recovery from liquid blanket systems for fusion reactor. In: Fusion Science and Technology. 2012 ; Vol. 61, No. 1 T. pp. 58-63.
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