DOI QR코드

DOI QR Code

A Study on Severe Accident Management Scheme using LOCA Sequence Database System

원자력발전소의 냉각재상실사고 특성DB를 활용한 중대사고 관리체계연구

  • Choi, Young (Korea Atomic Energy Research Institute) ;
  • Park, Jong-Ho (Department of Mechanical Engineering, Chungnam National University)
  • 최영 (한국원자력연구원 원자력융합기술개발부) ;
  • 박종호 (충남대학교 기계공학과)
  • Received : 2014.09.03
  • Accepted : 2014.12.04
  • Published : 2014.12.31

Abstract

In terms of an accident management, the cases causing severe core damage need to be analyzed and arranged systematically for an easy access to the results since the Three Mile Island (TMI) accident. The objectives of this paper are to explain how to identify the plant response and cope with its vulnerabilities using the probabilistic safety assessment (PSA) quantified results and severe accident database SARDB(Severe Accident Risk Data Bank) based on sequences analysis results. Although PSA has been performed for the Korean Standard Power Plants (KSNPs), and that it considered the necessary sequences for an assessment of the containment integrity. The developed Database (DB) system includes a graphical display for a plant and equipment status, previous research results by a knowledge-based technique, and the expected plant behaviour. The plant model used in this paper is oriented to the cases of loss of coolant accident (LOCA) is be used as a training simulator for a severe accident management.

Keywords

References

  1. USNRC, "Severe Accident Risks: An Assessment for Five US. Nuclear Power Plants", NUREG-1150, 1989.
  2. KOREA HYDRO & NUCLEAR POWER CO., LTD, "Probabilistic Safety Assessment for Hanul Units 3&4 [Level 1 PSA for External Events : Main Report]", 2004.
  3. K. I. Ahn and D. H. Kim, "Development of the Severe Accident Risk Information Database Management System, SARD", Korea Atomic Energy Research Institute, Vol. 35, pp. KAERI/TR-2378/2003, 2003.
  4. J. C. Lee and N. J. Mc Cormick, "Risk and Safety Analysis of Nuclear Systems", Wiley, 2011.
  5. KOREA HYDRO & NUCLEAR POWER CO., LTD, "Final Safety Analysis Report for Hanul Units 3&4", 2004.
  6. MAAP4: Modular Accident Analysis Program for LWR Plants, Code Manual Vols.1-4, Fauske & Associates, Inc., Burr Ridge, IL, Palo Alto, CA, USA, 1994.
  7. KEPRI, "Preliminary Study for Development of Accident Management Plans in Nuclear Power Plants", TR.96NJ11. 97.77, 1997.
  8. K. R. Kim, "Development of a Severe Accident Training Simulator: SATS," 2002 ANS Annual Meeting, Hollywood, 2002.

Cited by

  1. Prediction of golden time using SVR for recovering SIS under severe accidents vol.94, 2016, https://doi.org/10.1016/j.anucene.2016.02.029