Effects of simultaneous transfer of heat and tritium through Li-Pb or Flibe blanket

S. Fukada, Y. Edao, A. Sagara

Research output: Contribution to journalArticlepeer-review

9 Citations (Scopus)


Transport of tritium (T) and heat is calculated to estimate the performance of liquid Li17Pb83 (Li-Pb) or Li2BeF 4 (Flibe) as a T-breeder in a fusion reactor blanket. This bred in such a way of low leak to facilities outside and continuous recovery by a removal system, and heat is transferred through structural walls to He coolant efficiently. In this paper, T permeation in a blanket composed of structural materials and liquid Li-Pb or Flibe is calculated based on data of previous experiment. The effects of T recovery ratio by the outside removal apparatus and fluid-film T diffusion resistance in the liquid blanket on overall T permeation rates are analytically clarified. Design of a liquid blanket with low T leak and high T recovery is discussed here. In addition, possibility in that microbubbles may be generated at interfaces between a liquid blanket and a structural wall is investigated.

Original languageEnglish
Pages (from-to)1314-1319
Number of pages6
JournalFusion Engineering and Design
Issue number7-9
Publication statusPublished - Dec 2010

All Science Journal Classification (ASJC) codes

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


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