과제정보
본 논문은 한국에너지기술평가원(KETEP)의 지원으로 수행한 연구과제(No.20193110100020)의 결과입니다.
참고문헌
- USNRC, 2007, "Leak-Before-Break Evaluation Procedure, Rev. 1, Standard Review Plan 3.6.3", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG-0800.
- USNRC, 1984, "Evaluation of Potential for Pipe Break", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG-1061 Vol. 3.
- USNRC, 2002, "Development of Technical Basis for Leak-Before-Break Evaluation Procedure", U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6765.
- 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.
- 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.
- 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.
- 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.
- ABAQUS User's manual, Ver.2016, 2016, Dassault Systems.
- ASME BPVC Sec. III, 2004, "Rules for Construction of Nuclear Power Plant Component", American Society of Mechanical Engineers, NY.
- EPRI, 1987, "PICEP: Pipe Crack Evaluation Program", Report NP-3596-SR.
- Reg. Guide 1.92, Rev.5, 2012, "Combining Modal Reponses and Spatial Components in Seismic Response Analysis", U.S. Nuclear Regulatory Commission, Washington, DC.