A Risk Assessment for A Korean Standard Nuclear Power Plant

한국표준형 원전의 중대사고시 MACCS 코드를 이용한 위험성평가

  • Hwang, Seok-Won (Department of Nuclear Engineering, Hanyang University) ;
  • Jae, Moo-Sung (Department of Nuclear Engineering, Hanyang University)
  • 황석원 (한양대학교 원자력공학과) ;
  • 제무성 (한양대학교 원자력공학과)
  • Published : 2003.09.30

Abstract

The Level 3 PSA being termed accident consequence analysis is defined to assess effects on health and environment caused by radioisotopes released from severe accidents of nuclear power plants. In this study consequence analysis on health effects depending on release characteristics of radioisotopes has been peformed using the 3 MACCS code in severe accidents. The results of this study may contribute to identifying the relative importance of various parameters occurred in consequence analysis as well as to assessing risk reduction accident management strategies. Especially three parameters for the purpose of consequence analysis, such as the release height, the heat content, and the duration time, are used to analyze the variation of early fatalities and latent cancer fatalities. Also, in this study risk assessment using the concept, 'products of uncertainty and consequences', has been performed using consequence of MACCS and frequency on source term category 19 scenarios from IPE (Individual Plant Examination) analysis.

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