DOI QR코드

DOI QR Code

Leak Before Break Evaluation of Surge Line by Considering CPE under Beyond Design Basis Earthquake

설계초과지진시 CPE를 고려한 밀림관 파단전누설 평가

  • 김승현 (한국전력기술(주) 원자로설계개발단) ;
  • 김연정 (한국전력기술(주) 원자로설계개발단) ;
  • 이한걸 (한국전력기술(주) 원자로설계개발단) ;
  • 강선예 (한국전력기술(주) 원자로설계개발단)
  • Received : 2021.11.19
  • Accepted : 2022.06.20
  • Published : 2022.06.30

Abstract

Nuclear Power Plants (NPP) should be designed to have sufficient safety margins and to ensure seismic safety against earthquake that may occur during the plant life time. After the 9.12 Gyeongju earthquake accident, the structural integrity of nuclear power plants due to the beyond design basis earthquake is one of key safety issues. Accordingly, it is necessary to conduct structural integrity evaluations for domestic NPPs under beyond design basis earthquake. In this study, the Level 3 LBB (Leak Before Break) evaluation was performed by considering the beyond design basis earthquake for the surge line of a OPR1000 plant of which design basis earthquake was set to be 0.2g. The beyond design basis earthquake corresponding to peak ground acceleration 0.4g at the maximum stress point of the surge line was considered. It was confirmed that the moment behaviors of the hot leg and pressurized surge nozzle were lower than the maximum allowable loading in moment-rotation curve. It was also confirmed that the LBB margin could be secured by comparing the LBB margin through the Level 2 method. It was judged that the margin was secured by reducing the load generated through the compliance of the pipe.

Keywords

Acknowledgement

본 논문은 한국에너지기술평가원(KETEP)의 지원으로 수행한 연구과제(No.20193110100020)의 결과입니다.

References

  1. USNRC, 2007, "Leak-Before-Break Evaluation Procedure, Rev. 1, Standard Review Plan 3.6.3", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG-0800. 
  2. USNRC, 1984, "Evaluation of Potential for Pipe Break", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG-1061 Vol. 3. 
  3. USNRC, 2002, "Development of Technical Basis for Leak-Before-Break Evaluation Procedure", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6765. 
  4. Olson, R., Scott, P. and Wilkowski, G., 1992, "Application of a Nonlinear-Spring Element to Analysis of Circumferentially Cracked Pipe Under Dynamic Loading," ASME Pressure Vessels and Piping Conference, New Orleans, LA, June 21-25. 
  5. Olson, R., Wolterman, R., Scott, P., Krishnaswamy, P. and Wilkowski, G., 1994, "The Next Generation Analysis Methodology for Cracked Pipe Systems Subjected to Dynamic Loads," ASME Pressure Vessels and Piping Conference, 1994, Minneapolis, MN, June 19-23. 
  6. Wilkowski, G., Brust, B., Zhang, T., Hattery,G., Kalyanam, S., Shim, D-J., Kurth, E., Hioe, Y., Uddin, M. Johnson, J. J., Maslenikov, O. R., Gurpinar, A., Asfura, A. P., Sumodobila, B., Betervide, A. A. and Mazzantini, O., 2011, "Robust LBB Analyses for Atucha II Nuclear Plant", ASME Pressure Vessels and Piping Conference, Baltimore, Maryland, July 17-21. 
  7. Zhang, T., Frederick, W.B., Wilkowski, G., Xu, H., Alfredo, A.B. and Mazzantini, O., 2012, "LBB under Beyond Design Basis Seismic Loading", ASME Pressure Vessels and Piping Conference, 2012, Toronto, Ontario, July 15-19. 
  8. ABAQUS User's manual, Ver.2016, 2016, Dassault Systems. 
  9. ASME BPVC Sec. III, 2004, "Rules for Construction of Nuclear Power Plant Component", American Society of Mechanical Engineers, NY. 
  10. EPRI, 1987, "PICEP: Pipe Crack Evaluation Program", Report NP-3596-SR. 
  11. Reg. Guide 1.92, Rev.5, 2012, "Combining Modal Reponses and Spatial Components in Seismic Response Analysis", U.S. Nuclear Regulatory Commission, Washington, DC.