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Analysis of Radiological Consequences and its Characteristics in a typical BWR with a MARK-II Containment

  • Kyoko Funayama
  • Susumu Sumida
  • Mitsuhiro Kajimoto
Conference paper

Abstract

Nuclear Energy Safety Organization (JNES) has been carrying out a program of developing methodology of Level 3 PSA [1][2]. In the program, the MACCS2 code has been extensively applied to analyze radiological consequences for typical BWR and PWR plants in Japan. In addition, effects of accident management (AM), which have been implemented by industries, on radiological consequence for a typical BWR with a Mark-II containment have been discussing at JNES used with a developing methodology of Level 2 PSA [3].

Keywords

Steam Explosion Exposure Pathway Cancer Fatality Core Damage Radiological Consequence 
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.

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References

  1. 1.
    Ins/Nupec, Development of Methodology for Radiological Consequence in BWR, (in Japanese) INS/M02-36, 2003Google Scholar
  2. 2.
    Ins/Nupec, Level 2&3 PSA Study of BWR plants in Japan, (in Japanese), INS/M03-22, vol. 2, 2003Google Scholar
  3. 3.
    Ins/Nupec, Level 2 PSA Study of BWR plants in Japan, (in Japanese), INS/M02-11, 2003Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Kyoko Funayama
    • 1
  • Susumu Sumida
    • 1
  • Mitsuhiro Kajimoto
    • 1
  1. 1.Safety Evaluation and Analysis GroupJapan Nuclear Energy Safety OrganizationTokyoJapan

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