DOI QR코드

DOI QR Code

Uncertainty Analysis of Fire Modeling Input Parameters for Motor Control Center in Switchgear Room of Nuclear Power Plants

원자력발전소 모터제어반 스위치기어실 화재 모델링 입력변수 불확실성 분석

  • 강대일 (한국원자력연구원 종합안전평가부) ;
  • 양준언 (한국원자력연구원 종합안전평가부) ;
  • 유성연 (충남대학교 기계설계학과)
  • Received : 2011.12.29
  • Accepted : 2012.04.13
  • Published : 2012.04.30

Abstract

This paper presents the uncertainty analysis results of fire modeling input parameters for motor control center in switchgear room of nuclear power plants. FDS (Fire Dynamics simulator) 5.5 was used to simulate the fire scenario and Latin Hyper Cube Monte Carlo simulations were employed to generate random samples for FDS input parameters. The uncertainty analysis results of input parameters are compared with those of the model uncertainty analysis and sensitivity analysis approaches of NUREG-1934. The study results show that the input parameter uncertainty analysis approach may lead to more conservative results than the uncertainty analysis and sensitivity analysis methods of NUREG-1934.

본 논문에서는 원자력발전소의 모터제어반 스위치기어실 화재 모델링에 대한 입력변수 불확실성 분석을 수행하였다. 화재모델링은 FDS 5.5를 사용하였고 FDS 입력변수 램던 샘플링은 라틴하이퍼쿠브 몬테칼로 방법을 이용하였다. 본 연구에서 수행한 입력변수 불확실성 분석 결과를 비교하기 위해 NUREG-1934의 화재모델링 결정론적 불확실성 분석과 민감도 분석 방법을 이용한 분석도 수행하였다. 분석결과, 본 연구의 모터제어반 스위치 기어룸 화재 모델링에 대한 입력변수 불확실성 분석방법이 NUREG-1934의 방법보다 보수적인 결과를 얻을 수 있음을 확인하였다.

Keywords

References

  1. NFPA, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plant", NFPA 805, 2001 Edition(2003).
  2. ASME, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications", ASME/ANS RA-Sa- 2009, ASME(2009).
  3. Mahammad Modarres, "Risk Analysis in Engineering: Techniques, Tools, and Trends", CRC Press(2006).
  4. J. Dreisbach, D. Stroup, F. Joglar, D. Birk, and B. Najafi, "Nuclear Power Plant Fire Modeling Application Guide(NPP FIRE MAG)(2nd Draft)", NUREG-1934, USNRC(2011).
  5. M. Drouin, G. Parry, J. Lehner, G. Martinez-Guridi, J. LaChance, and T. Wheeler, "Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making", NUREG-1855, Volume 1, USNRC(2009).
  6. W. Jones, R. Peacock, G. Forney, and P. Reneke, "CFAST: An Engineering Tool for Estimating Fire Growth and Smoke Transport", Version 5 - Technical Reference Guide, NIST Special Publication 1030, National Institute of Standards and Technology, Gaithersburg, MD(2004).
  7. Kevin McGrattan, Randall McDermott, Simo Hostikka, and Jason, Floyd, "Fire Dynamics Simulator (Version 5) User's Guide", NIST Special Publication 1019-5, National Institute of Standards and Technology, FDS Version 5.5, Gaithersburg, MD(2010).
  8. Siu Kui Aua, Zhi-Hua Wangb, and Siu-Ming Loa, "Compartment Fire Risk Analysis by Advanced Monte Carlo Simulation", Engineering Structures Vol.29, pp.2381-2390(2007). https://doi.org/10.1016/j.engstruct.2006.11.024
  9. Rochan R. Upadhyay and Ofodike A. Ezekoye, "Treatment of Design Fire Uncertainty Using Quadrature Method of Moments", Fire Safety Journal, Vol.43, pp.127-139(2008). https://doi.org/10.1016/j.firesaf.2007.06.005
  10. Tom Elicson, "Addressing Uncertainty in Detailed Fire Modeling of Nuclear Power Plant Single Compartment Fire Scenarios Using Latin Hypercube Sampling", PSA 2008 Topical Meeting, USA(2008).
  11. Victor Ontiveros, Adrien Cartillier, and Mohammad Modarres, "An Integrated Methodology for Assessing Fire Simulation Code Uncertainty", Nuclear Science and Engineering, Vol.166, No.33, pp.179-201(2010). https://doi.org/10.13182/NSE10-05
  12. Tor Lindstroom and David Lund, "A Method of Quantifying User Uncertainty in FDS by Using Monte Carlo Analysis", Department of Fire and Safety Engineering, Lund University, Lund(2009).
  13. John C. Lee and Norma J. McCormick, "Risk and Safety Analysis of Nuclear Systems", Wiley(2011).
  14. IAEA, "Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation", Safety Report Series No.52, IAEA, Vienna(2008).
  15. Mohammad Pourgol-Mohamad, Mohammad Modarres, and Ali Mosleh, "Integrated Methodology for Thermal-Hydraulic Code Uncertainty Analysis with Application", Nuclear Technology, Vol.165, pp.333- 359(2009). https://doi.org/10.13182/NT165-333
  16. B. Najafi, S.P. Nowlen, F. Joglar, D. Funk, R.C. Anoba, M. Kazarians, F. Wyant, A. Kolaczkowski, G. Hannaman, and J. Forester, "Fire PRA Methodology for Nuclear Power Facilities", NUREG/CR-6850, USNRC(2005).
  17. Training material for "8/1/2011-8/5/2011 EPRI/ NRC-RES Fire PRA Course: Module 5- Advanced Fire Modeling", USNRC(2011).
  18. SFPE, "SFPE Handbook of Fire Protection Engineering", 4th Edition, National Fire Protection Association(2008).
  19. K. McGrattan, K. Hill, J. Dreisbach, F. Joglar, and B. Najafi, "Verification & Validation of Selected Fire Models for Nuclear Power Plant Applications Vol.7: Fire Dynamics Simulator", NUREG-1824, USNRC(2007).
  20. H.G. Lim, S.H. Han, and J.J. Jeong, "MOSAIQUE: A Network Based Software for Probabilistic Uncertainty Analysis of Computerized Simulation Models", Nuclear Engineering and Design, Vol.241, No.5, pp.1776-1784(2011). https://doi.org/10.1016/j.nucengdes.2011.01.021