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

S. Fukada, Y. Edao, A. Sagara

研究成果: ジャーナルへの寄稿記事

7 引用 (Scopus)

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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.

元の言語英語
ページ(範囲)1314-1319
ページ数6
ジャーナルFusion Engineering and Design
85
発行部数7-9
DOI
出版物ステータス出版済み - 12 2010

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All Science Journal Classification (ASJC) codes

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

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