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Application of Probabilistic Safety Analysis in Design and Maintenance of the ABWR

  • Masahiko Fujii
  • Shinichi Morooka
  • Hideaki Heki
Chapter

Abstract

A brief history of the development of nuclear reactor in Japan is summarized in Fig. 1.1s. In the 1960s, nuclear reactor technology was introduced mainly from the United States. But in this era, the capacity factor of Japanese boiling water reactors (BWRs) is low because of initial problems such as stress corrosion cracking (SCC). A program to improve the nuclear reactor performance was started. In the 1970s, phases-I and -II of this program was carried out for the purpose of improvement, standardization, and localization of conventional light water reactors (LWRs). The final stage of this program was carried out in the 1980s to develop advanced reactors (both ABWR and APWR), which had to meet the following objectives.

Keywords

Reactor Pressure Vessel Multiple Failure Conceptual Design Stage Reactor Building Probabilistic Safety Analysis 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

References

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    Sato T, Tanabe A, Kondo S (1995) PSA in design of passive/active safety reactors. Reliab Eng Syst Saf 50:17–32CrossRefGoogle Scholar

Copyright information

© Springer Science+Business Media, LLC 2011

Authors and Affiliations

  • Masahiko Fujii
    • 1
  • Shinichi Morooka
    • 1
  • Hideaki Heki
    • 1
  1. 1.Toshiba CorporationTokyoJapan

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