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Journal of the Korean Nuclear Society = 원자력학회지 v.36 no.6, 2004년, pp.485 - 496   피인용횟수: 1

Determination of Performance Indicator Thresholds Based on Typical PSA Results

Kang, Dae-Il    (Korea Atomic Energy Research Institute   ); Kim, Kil-Yoo    (Korea Atomic Energy Research Institute   ); Hwang, Mee-Jung    (Korea Atomic Energy Research Institute   ); Sung, Key-Yong    (Korea Institute of Nuclear Safety  );
  • 초록

    Typical probabilistic safety assessment (PSA) results were used to estimate the performance indicator (PI) thresholds of unplanned reactor scram (URS) and safety system unavailability (SSU) for Korean nuclear power plants (NPPs). The changes in core damage frequency ( ${\Delta}$ CDFs) of $10^{-6}/yr$ , $10^{-5}/yr$ , and $10^{-4}/yr$ were adopted as the risk criteria in setting up the PI thresholds. The PI thresholds for the URS were estimated using information pertaining to the initiating event frequencies, the CDF, and the CDF contribution of each initiating event. The PI thresholds of the SSU were estimated using information on the unavailability, the Fussell-Vesely importance, and the CDF.


  • 주제어

    performance indicator thresholds .   unplanned reactor scram .   safety system unavailability .   probabilistic safety assessment .   core damage frequency.  

  • 참고문헌 (19)

    1. D.I Kang et aI., 'Development on the Application Technology of Risk-Based Performance Indicator for Korean NPPs (in Korean)', KINS/HR-584, KINS, (2004) 
    2. D. I Kang et aI., 'A Study of the State of the Art on the Determination of the Threshold Values of the Performance Indicators for Safety Systems and Initiating Events of Nuclear Power Plants (in Korean)', KAERI/AR-698/2004, KAERI, (2004) 
    3. USNRC, 'Rector Oversight Process', NUREG1649.Rev.3, (2000) 
    4. USNRC, 'Risk-Based Performance Indicators: Results of Phase I Development.' NUREG-1753, NRC, (2002) 
    5. USNRC, 'Reactor Oversight Process SelfAssessment for Calendar Year 2003', SECY04-0053, NRC, (2004) 
    6. Patrick W.Baranowsky and Donald A. Dube, 'Mitigating Systems Performance Index', seminar material (presentation to ACRS subcommittees on reliability and PRA, and plant operations), USNRC, (2003) 
    7. S. Chakraborty et a!', 'Risk-Based Safety Performance Indicators for Nuclear Power Plants', SMIRT17, Prague, Czech Republic, August 17-22, (2003) 
    8. USNRC, 'Recommendations for Reactor Oversight Process Improvements', SECY -99-007, Appendix H, NRC, (1999) 
    9. USNRC, 'Recommendations for Reactor Oversight Process Improvements(Follow-up to SECY 99-007)' , SECY-99-007A, NRC, (1999) 
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    15. Wall, I.B and Worledge, D. H., 'Some Perspectives on Risk Importance Measures', In Proceedings of PSA '96, p 203-208, Park City Utah, September 29-0ctober 3, (1996) 
    16. Kil-You Kim et aI., 'A Study on Importance Measures for Risk-Informed Regulation & Applications (in Korean)', KAERI/TR- 2432/2003, KAERI, (2003) 
    17. . NRC, 'Draft Overview of the Development of Mitigating Systems Performance Indices (MSPls)' , ADMAS accession number ML031360121, NRC, (2003) 
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    19. Mee-Jung Hwang et al., 'A Study on Maintenance Rule Program and Its Application to Korean NPP(in Korean)' , Rev.1, KAERl/TR-1788/2001, KAERI, (2001) 
  • 이 논문을 인용한 문헌 (1)

    1. 2011. "" Nuclear engineering and technology : an international journal of the Korean Nuclear Society, 43(2): 105~132     

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