Journal of the Korean Society of Safety (한국안전학회지)

The Korean Society of Safety (한국안전학회)
권호 표지
DOI QR코드

DOI QR Code

Fire Simulations for the Abandonment Risk Assessment of Main Control Room Fire in Domestic Nuclear Power Plant

국내 원자력발전소의 주제어실 화재 피난 리스크 평가를 위한 화재 시뮬레이션

  • 강대일 (한국원자력연구원 종합안전평가부) ;
  • 김길유 (한국원자력연구원 종합안전평가부) ;
  • 장승철 (한국원자력연구원 종합안전평가부) ;
  • 유성연 (충남대학교)
  • Received : 2014.05.13
  • Accepted : 2014.08.05
  • Published : 2014.08.31
Download PDF
⟨ Previous Next ⟩

Abstract

In this paper, to systematically assess the abandonment risk of main control room (MCR) fire, fire simulations with Fire Dynamics Simulator were performed and abandonment probabilities were estimated for the MCR bench-board fire of domestic reference nuclear power plant. The fire simulation scenarios performed in this study included propagating and non-propagating fires of the MCR bench-board, and the availability and unavailability of heating, ventilation, and air conditioning system (HVACS). The following results were obtained. First, temperature was the major abandonment impact factor for the MCR bench-board fire if the HVACS was available and optical density was that if the HVACS was unavailable. Second, the fire scenario contributing the MCR bench-board fire abandonment risk was identified to be only the propagating fire. Third, it was confirmed that the abandonment probability of the MCR bench-board fire for domestic reference nuclear power plant could be reduced by using the fire modeling.

Keywords

References

  1. H. J. Kim, "Nuclear Safety and Regulation", Hans House, Korea, 2012.
  2. J. C. Lee and N. J. McCormick, "Risk and Safety Analysis of Nuclear Systems", Wiley, 2011.
  3. H. -J. Jeon, "A Risk Impact Assessment According to the Reliability Improvement of the Emergency Power Supply System of a Nuclear Power Plant", Journal of the Korean Society of Safety, Vol. 27, No. 5, pp. 224-228, 2012.
  4. W. J. Parkinson, K.M.Bateman, W.S.Gough, J.A.Lee, B.Najafi, J.Schloss and G.Simon, "Fire PRA Implementation Guide", EPRI TR-105928, 1995.
  5. 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.
  6. KOREA HYDRO & NUCLEAR POWER CO., LTD., "Probabilistic Safety Assessment for Hanul Units 3&4 [Level 1 PSA for External Events : Main Report]", 2004.
  7. Usama Farradj and Kiang Zee, "Insights from Evaluations of Control Room Abandonment Fire PRA Analysis", PSA 2008 Topical Meeting, USA, 2008.
  8. Ashley Mossa, "Abandonment Analyses for a Fire in a Nuclear Power Plant Control Room", Master's thesis, Rensselaer Polytechnic Institute, 2010.
  9. M. A. Minton, " Uncertainty and Sensitivity Analysis of a Fire-induced Accident Scenario Involving Binary Variables and Mechanistic Code", Master's Thesis, Massachusetts Institute of Technology, 2010.
  10. S. Zhong, "Abandonment Times Evaluation of Main Control Room at Daya Bay Nuclear Plant", 11th International Probabilistic Safety Assessment and Management Conference & the Annual European Safety and Reliability Conference, Finland, 2012.
  11. D. Stroup et al., "Nuclear Power Plant Fire Modeling Application Guide(NPP FIRE MAG)", NUREG-1934, USNRC, 2012.
  12. J. Francisco and R. Guy, "Modeling Main Control Room Fire", PSA 2013 Topical Meeting, USA, 2013.
  13. 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.
  14. K. McGrattan, R. McDermott, S. Hostikka and J. 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.
  15. D. Il. Kang, S. H. Han and S. Y. Yoo, " Development of the IPRO-ZONE for Internal Fire Probabilistic Safety Assessment", Nuclear Engineering and Design, Vol. 257, page 72-78, 2013. https://doi.org/10.1016/j.nucengdes.2013.01.014
  16. K. Canavan and J.S. Hyslop, "Fire Probabilistic Risk Assessment Methods Enhancements", NUREG/CR-6850 Supplement 1, USNRC, 2010.
  17. S.Lewis et al., "EPRI/NRC-RES Fire Human Reliability Analysis Guidelines", NUREG1-1921, USNRC, 2012.
  18. SFPE , "SFPE Handbook of Fire Protection Engineering", 4th Edition, National Fire Protection Association, 2008.
  19. Naeem Iqbal and Mark Henry Salley, "Fire Dynamics Tools (FDTs): Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program", NUREG-1805, USNRC, 2004.
  20. KOREA HYDRO & NUCLEAR POWER CO., LTD,. "Final Safety Analysis Report for Hanul Units 3&4", 2004.
  21. ASME, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications", ASME/ANS RA-Sa-2009, ASME, 2009.

Cited by

  1. A Study on Severe Accident Management Capabilities and Strategies for CANDU Reactor vol.29, pp.5, 2014, https://doi.org/10.14346/JKOSOS.2014.29.5.160