DOI QR코드

DOI QR Code

Systems Engineering Process Approach to the Probabilistic Safety Assessment for a Spent Fuel Pool of a Nuclear Power Plant

사용후핵연료저장조의 확률론적안전성평가 수행을 위한 시스템엔지니어링 프로세스 적용 연구

  • Choi, Jin Tae (Dept. of Industrial Engineering, Kumoh National Institute of Technology) ;
  • Cha, Woo Chang (Dept. of Industrial Engineering, Kumoh National Institute of Technology)
  • 최진태 (금오공과대학교 산업공학과) ;
  • 차우창 (금오공과대학교 산업공학과)
  • Received : 2021.10.18
  • Accepted : 2021.12.16
  • Published : 2021.12.31

Abstract

The spent fuel pool (SFP) of a nuclear power plant functions to store the spent fuel. The spent fuel pool is designed to properly remove the decay heat generated from the spent fuel. If the cooling function is lost and proper operator action is not taken, the spent fuel in the storage pool can be damaged. Probabilistic safety assessment (PSA) is a safety evaluation method that can evaluate the risk of a large and complex system. So far, the probabilistic safety assessment of nuclear power plants has been mainly performed on the reactor. This study defined the requirements and the functional architecture for the probabilistic safety assessment of the spent fuel pool (SFP-PSA) by applying the systems engineering process. And, a systematic and efficient methodology was defined according to the architecture.

Keywords

Acknowledgement

본 연구는 금오공과대학교 2021 학술 연구비로 지원되었음.

References

  1. 박창규, 하재주, 확률론적 안전성 평가, 브레인코리아, 2003
  2. T.E. Collins, G. Hubbard, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants, U.S. Nuclear Regulatory Commission, NUREG-1738, 2001
  3. E. Burns, L. Lee, A. Duvall, R. Kirchner, F. Gallo, PWR Spent Fuel Pool Risk Assessment Integration Framework and Pilot Plant Application, Electric Power Research Institute, TR-3002002691, 2014
  4. 김효원, 사용후핵연료 저장수조 사고의 확률론적 리스크 평가, 한양대학교, 2014
  5. ISO/IEC 15288, Systems and Software Engineering - System Life Cycle Processes 2nd Edition, 2008
  6. Alexander Kossiakoff, Systems Engineering Principles and Practice 2ndEdition, John Wiley&sons, p36-37, 2011
  7. Standard for Application and Management of the Systems Engineering Process, IEEE Std 1220. Washington, DC, 1998
  8. INCOSE, Systems Engineering Handbook, 4th Edition, Edited by T. M. S. David D. Walden, Garry J. Roedler, Kevin J. Forberg, R. Douglas Hamelin, Hoboken, New Jersey, p106-128, p129-140, 2015
  9. Korea Institute of Nuclear Safety, Level 1 PSA Regulatory Guidelines, Rev. 02, KINS/RG-N16.05, 2021
  10. Korea Institute of Nuclear Safety, Chapter 16 Severe Accident and Risk Assessment, Rev. 02, KINS/RS-N16.00, 2016
  11. ASME/ANS RA-Sa-2009, Addenda to ASME/ANS RA-S-2008 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME, 2009
  12. KEPCO-E&C, E-P-NU-907-1.3, SAREX 1.3 Software Registration, 2016