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The Development of a Human Reliability Analysis System for Safety Assessment of a Nuclear Power Plants

  • Journal of The Korea Society of Computer and Information
  • Abbr : JKSCI
  • 2006, 11(6), pp.261-268
  • Publisher : The Korean Society Of Computer And Information
  • Research Area : Engineering > Computer Science

김승환 1 JUNG WON DEA 2

1한국원자력연구소
2한국원자력연구원

Candidate

ABSTRACT

In order to perform a probabilistic safety assessment (PSA), it requires a large number of data for various fields. And the quality of a PSA results have become more important thing of the risk assessment . As part of enhancing the PSA quality, Korea Atomic Energy Research Institute is developing a full power Human Reliability Analysis (HRA) calculator to manage human failure events (HFEs) and to calculate the diagnosis human error probabilities and execution human error probabilities. This paper introduces the development process and an overview of a standard HRA method for nuclear power plants. The study was carried out in three stages; 1) development of the procedures and rules for a standard HRA method, 2) design of a system structure, 3) development of the HRA calculator.

Citation status

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