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Studies on Materials for Heavy-Liquid-Metal-Cooled Reactors in Japan

[+] Author Affiliations
Minoru Takahashi, Masayuki Igashira, Toru Obara, Hiroshi Sekimoto

Tokyo Institute of Technology, Tokyo, Japan

Kenji Kikuchi

Japan Atomic Energy Research Institute, Tokai, Ibaraki, Japan

Kazumi Aoto

Japan Nuclear Cycle Development Institute, O-arai, Ibaraki, Japan

Teruaki Kitano

Mitsui Engineering & Shipbuilding Company, Ltd., Tokyo, Japan

Paper No. ICONE10-22166, pp. 549-559; 11 pages
doi:10.1115/ICONE10-22166
From:
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 2
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3596-0 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME

abstract

Recent studies on materials for the development of lead-bismuth (Pb-Bi)-cooled fast reactors (FR) and accelerator-driven sub-critical systems (ADS) in Japan are reported. The measurement of the neutron cross section of Bi to produce 210 Po, the removal experiment of Po contamination and steel corrosion test in Pb-Bi flow were performed in Tokyo Institute of Technology. A target material corrosion test was performed in the project of Transmutation Experimental Facility for ADS in Japan Atomic Energy Research Institute (JAERI). Steel corrosion test was started in Mitsui Engineering & Shipbuilding Co., LTD (MES). The feasibility study for FR cycle performed in Japan Nuclear Cycle Institute (JNC) are described.

Copyright © 2002 by ASME

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