Nuclear Engineering and Technology

  • 제36권1호
  • /
  • Pages.83-103
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  • 2004
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

A Formal Guidance for Handling Different Uncertainty Sources Employed in the Level 2 PSA

  • 발행 : 2004.02.01
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초록

The methodological framework of the Level 2 PSA appears to be currently standardized in a formalized fashion, but there have been different opinions on the way the sources of uncertainty are characterized and treated. This is primarily because the Level 2 PSA deals with complex phenomenological processes that are deterministic in nature rather than random processes, and there are no probabilistic models characterizing them clearly. As a result, the probabilistic quantification of the Level 2 PSA CET / APET is often subjected to two sources of uncertainty: (a) incomplete modeling of accident pathways or different predictions for the behavior of phenomenological events and (b) expert-to-expert variation in estimating the occurrence probability of phenomenological events. While a clear definition of the two sources of uncertainty involved in the Level 2 PSA makes it possible to treat an uncertainty in a consistent manner, careless application of these different sources of uncertainty may produce different conclusions in the decision-making process. The primary purpose of this paper is to characterize typical sources of uncertainty that would often be addressed in the Level 2 PSA and to provide a formal guidance for quantifying their impacts on the PSA Level 2 risk results. An additional purpose of this paper is to give a formal approach on how to combine random uncertainties addressed in the Level 1 PSA with subjectivistic uncertainties addressed in the Level 2 PSA.

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참고문헌

  1. Individual Plant Examination: Submittal Guidance, NUREG-1335, Final Report (August 1989)
  2. U.S. Nuclear Regulatory Commission, Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, Vols. 1 & 2, NUREG-1150, Washington, DC (December 1990)
  3. A. Torri, P.P. Bieniarz, and D. Haschke, 'Experiences and Insights from Level 2 PSAs', Intl. Meeting on PSA/PRA and Severe Accidents '94, Ljubljana, Slovenia, (April 17-20, 1994)
  4. A.S. Kuritzky, R. Vijaykumar, and M. Khatib-Rahbar, 'Observations from Review of Several IPE Back-End Submittals and Other Level 2 PRA Studies,' Intl. Meeting on PSA/PRA and Severe Accidents '94, Ljubljana, Slovenia (April 17-20 1994)
  5. K.I. Ahn, Y.H. Jin, D.H. Kim, and C.K. Park, 'A Comparative Assessment of the Current Containment Event Tree Methodologies,' Journal of the Korean Nuclear Society, Vol. 26 (4), pp.611-626 (December 1994)
  6. SARRP Review Committee, A Review of the Severe Accident Risk Reduction Program (SARRP) Containment Event Trees, Prepared for U.S. Nuclear Regulatory Commission, NUREG/CR-4569 (May 1986)
  7. B.J. Breeding, J.C. Helton, W.B. Murfin, and L.N. Smith, Evaluation of Severe Accident Risks: Surry Unit 1 Appendices, NUREG/CR-4551, Vol.3, Rev.1, Part 2, Prepared for U.S. NRC, Sandia National Laboratories, Albuquerque, NM (October 1990)
  8. K.I. Ahn, D.H. Kim, and J.E. Yang, 'Methodologies for Uncertainty Analysis in the Level 2 PSA and Their Implementation Procedures, KAERI/TR-2151/2002, Korea Atomic Energy Research Institute, (April 2002)
  9. G. Apostolakis, 'The Concept of Probability in Safety Assessments of Technological Systems,' Science, Vol.250, pp.1359-1364 (1990) https://doi.org/10.1126/science.2255906
  10. R.L. Winkler, 'Uncertainty in Probabilistic Risk Assessment,' Reliability Engineering and System Safety, Vol.54, pp.127-132 (1996) https://doi.org/10.1016/S0951-8320(96)00070-1
  11. K.I. Ahn and J.E. Yang, 'The Explicit Treatment of Model Uncertainties in the Presence of Aleatory and Epistemic Parameter Uncertainties in Risk and Reliability Analysis,' Journal of the Korean Nuclear Society, Vol.35 (1), pp.64-79 (February 2003)
  12. S. Kaplan, 'Matrix Theory Formalism for Event Tree Analysis Application to Nuclear-Risk Analysis', Risk Analysis, Vol. 2, pp.9-18 (1981) https://doi.org/10.1111/j.1539-6924.1982.tb01398.x
  13. A. Torri, 'A Consistent Probabilistic Methodology for the Seabrook Station Containment Event Tree Analysis,' ANS/ENS Intl. Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, CA (February 24-March 1, 1985)
  14. D.Y. Hsia, J.S. Chung, Y.C. Chou, R. Sherry, J. Fulford, and G. Parry, 'Containment Event Tree Analysis for the Kuosheng BWR 6/Mark III Plant,' ANS/ENS Intl. Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, CA (February 24-March 1 1985)
  15. SAIC, Generic Framework for IPE Back-End (Level 2) Analysis, Volume 2: PWR Implementation Guidelines, NSAC-159, Volume 2 (October 1991)
  16. K.I. Ahn and Y. Jin, 'A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis,' Nuclear Technology, Vol. 116 (2), pp.146-159 (1996)
  17. M.L. Corradini, D.V. Swenson, and R.L. Woodfin, 'Analysis of Containment Failure Due to a Steam Explosion Following a Postulated Core Melt Down in a Light-Water Reactor,' Nuclear Safety, Vol.23 (1), pp.21-31 (January-February 1982)
  18. E. Hofer, 'When to separate uncertainties and when not to separate,' Reliability Engineering and System Safety, 54, pp.113-118 (1996) https://doi.org/10.1016/S0951-8320(96)00068-3
  19. A.S. Benjamin, G.R. Boyd, W.B. Murfin, and D.M. Kunsman, 'Evaluation of Uncertainties in Risk Estimating from A number of Severe Accident Issues,' Nuclear Engineering and Design, Vol.104, pp.249-266 (1987) https://doi.org/10.1016/0029-5493(87)90203-2
  20. KEPCO, Korean Standard Power Plant Ulchin Units 3&4: Final Probabilistic Safety Assessment Report (1996)
  21. A. Mosleh and V.M. Bier, 'Uncertainty about Probability: a Reconciliation with the Subjective Viewpoint,' IEEE Trans. on Systems, Man, and Cybernetics - Part A: Systems and Humans, Vol.26 (3), pp.303-310 (May 1996) https://doi.org/10.1109/3468.487956
  22. R. Hummel and L. Manevitz, 'A Statistical Approach to the Representation of Uncertainty in Beliefs using Spread of Opinions,' IEEE Trans. on Systems, Man, and Cybernetics-Part A: Systems and Humans, Vol.26 (3), pp.378-384 (1996) https://doi.org/10.1109/3468.487962
  23. K.I. Ahn, J.E. Yang, and J.J. Ha, 'The Plant-specific Impact of Different Pressurization Rates in the Probabilistic Estimation of Containment Failure Modes,' Journal of the Korean Nuclear Society, Vol.35 (2), pp.154-164 (April 2003)
  24. K.I. Ahn and Y.H. Jin, CONPAS 1.0 (CONtainment Performance Analysis System) Code Package Users' Manual, KAERI Technical Report (in Korean), KAERI/TR651/96 April (1996)