Communications for Statistical Applications and Methods

The Korean Statistical Society (한국통계학회)
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Probabilistic Safety Assessment of Nuclear Power Plants Using Bayes Method

  • Shim, Kyu-Bark (Department of Information and Statistics, Dongguk University)
  • Published : 2001.08.01
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Abstract

A commercial nuclear power station contains at least tow emergency diesel generators(EDG) to control the risk of severe core damage during station blackout accidents. Therefore, the reliability of the EDG's to start and load-run on demand must be maintained at a sufficiently high level. Probabilistic safety assessments(PSA) are increasingly being used to quantify the public risk of operating potentially hazardous systems such as nuclear power reactors. In this paper, to perform PSA, we will introduce three different types of data and use Bayes procedure to estimate the error rate of nuclear power plant EDG, and using practical examples, illustrate which method is more reasonable in our situation.

Keywords

References

  1. Nuclean Science and Engineering v.70 Expert opinion and Statistical Evidence:An Application to Reactor Core Melt Frequency Apostolakis,G.;Mosleh,A.
  2. Journal of the American Statistical Association v.91 no.436 The Notion of Composite Reliabilityand Its Hierarchical Bayes Estimation Chen,J.;Singpurwalla,N.D.
  3. Journal of KIIS v.12 no.3 Development Procedure fo Generic Component Reliability Data Basein PSA and Its Application Hwang,M.J.;Kim,K.Y.;Lim,T.J.;Jung,W.D.;Kim,T.W.
  4. Survey and Analysis of the Loss Off-Site Power Events on Korean Nuclear Power Plants and the Reliabibity/Unavailiability of Emergency Diesel Generators of Kori 3, 4, Kim,T.W.
  5. Applies Statistics v.47 The binomial failure rate mixture model for common cause failure data from the nuclear industry Kvam,P.H.
  6. Empirical Bayes Methods(2nd ed.) Maritz,J.S.;Lwin,T.
  7. Nuclean Science and Engineering v.83 On Combining Data for Estimating the Frequency of Low-Probalibity Events with Application to Sodium Valve Failure Rates Martz,H.F.;Bryson,M.C.
  8. Nuclear Safety v.25 Assessing Compatibility with Reactor Safety Goals Using Uncertain Risk Analysis with Application to Core Melt Martz,H.F.;Johnson,J.W.
  9. Technometrics v.38 no.1 Empirical Bayes Estimation of the Reliability of Nuclear Power Plant Emergency Diesel Generators Martz,H.F.;Kvam,H.K.;Abramson,L.R.
  10. Nuclear Safety v.38 no.1 Assessing Conformance to Safety Goals Using Nonparametric Empirical Bayes Methods:A Nuclear Reactor Application Martz,H.F.;Johnson,J.W.
  11. Technometrics v.41 no.4 Estimation of Trends in the Scram Rate at Nuclear Power Plants Martz,H.F.;Parker,R.L.;Rasmuson,D.M.
  12. USNRC Report WASH-1400-MR(NUREG-75/014) Reactor Safety Study:An assessment of accident Rishs in U.S. Commericial Nuclear Power Plants Rasmussen,N.C.
  13. Journal of the Korean Society for Quality Control v.25 no.3 Bayes Estimate for the Reliability of Nuclear-Power Plant Emergeney Diesel Generator Shim,K.B.
  14. Reliability Engineering and System Safety v.46 Failure of Emergency Diesel Generators:A population Analysis Using Empirical Bayes Methods Vesely,W.E.;Uryasev,S.P.;Samanta,P.K.
  15. The Reliability of Emergency Diesel Generators at U.S. Nuclear Power Plants Wycoff,H.
  16. 월성1호기 신뢰도 업무 현황 및 디젤발전기 신뢰도 분석 보고서 한국원자력 연구소