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

S. Fukada; Y. Edao; A. Sagara

doi:10.1016/j.fusengdes.2010.03.032

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

S. Fukada, Y. Edao, A. Sagara

Engineering Science for Advanced energy system

Research output: Contribution to journal › Article › peer-review

9 Citations (Scopus)

Abstract

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 language	English
Pages (from-to)	1314-1319
Number of pages	6
Journal	Fusion Engineering and Design
Volume	85
Issue number	7-9
DOIs	https://doi.org/10.1016/j.fusengdes.2010.03.032
Publication status	Published - 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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10.1016/j.fusengdes.2010.03.032

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title = "Effects of simultaneous transfer of heat and tritium through Li-Pb or Flibe blanket",

abstract = "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.",

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T1 - Effects of simultaneous transfer of heat and tritium through Li-Pb or Flibe blanket

AU - Fukada, S.

AU - Edao, Y.

AU - Sagara, A.

PY - 2010/12

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AB - 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.

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ER -

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

Abstract

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