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The Risk Effect Analysis of the Digital Safety-Critical Systems in a Nuclear Power Plant

  • Hyun Gook Kang
  • Seung-Cheol Jang
  • Jaejoo Ha
Conference paper

Abstract

The impact analysis of digital safety-critical systems, the digital plant protection system and the digital engineered safety feature actuation system, on plant risk is embodied and illustrated based on the digital systems’ fault-tree models combined with a typical PSA model of a Korean Standard Nuclear Power Plant. This paper presents the sensitivity study results which used three variables: human failure probability, software failure probability and watchdog timer coverage. The result quantitatively shows that plant risk largely depends on these variables.

Keywords

Nuclear Power Plant Failure Probability Digital System Fault Tree Korea Atomic Energy Research Institute 
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References

  1. 1.
    H.G. Kang and T. Sung, An analysis of safety-critical digital systems for risk-informed design, Reliability Engineering and Systems Safety, Vol. 78, 2002.Google Scholar
  2. 2.
    S.H. Han, et al., “PC Workstation-Based Level 1 PRA Code Package KIRAP,” Reliability Engineering and Systems Safety, Vol.30, pp.313–322, 1990CrossRefGoogle Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Hyun Gook Kang
    • 1
  • Seung-Cheol Jang
    • 1
  • Jaejoo Ha
    • 1
  1. 1.Integrated Safety Assessment DivisionKorea Atomic Energy Research InstituteYuseong, DaejeonKorea

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