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Design of Material Strength Test in Lead-Bismuth Flow

[+] Author Affiliations
Masatoshi Kondo, Minoru Takahashi

Tokyo Institute of Technology, Tokyo, Japan

Koji Hata

Nuclear Development Corporation, Tokai, Ibaraki, Japan

Paper No. ICONE10-22736, pp. 959-962; 4 pages
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 4
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3598-7 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME


Liquid lead and lead-bismuth have drawn the attention as one of the candidate coolants of the fast breeder reactors (FBRs), and the accelerator driven transmutation systems (ADSs). In order to use the coolant to the systems, the physical and chemical characteristics of the heavy metals are necessary. This plan has been proposed for the strength test of materials in the liquid metal surroundings. The lead-bismuth circulation loop with the strength test has been designed, and the strength test of candidate materials has been planned.

Copyright © 2002 by ASME



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