- Volume 24 Issue 8 Serial No. 179
DOI QR Code
Development of a RVIES Syetem for Reactor Vessel Integrity Evaluation
원자로용기 건전성평가를 위한 RVIES 시스템의 개발
- Published : 2000.08.01
In order to manage nuclear power plants safely and cost effectively, it is necessary to develop integrity evaluation methodologies for the main components. Recently, the integrity evaluation techniques were broadly studied regarding the license renewal of nuclear power plants which were approaching their design lives. Since the integrity evaluation process requires special knowledges and complicated calculation procedures, it has been allowed only to experts in the specified area. In this paper, an integrity evaluation system for reactor pressure vessel was developed. RVIES(Reactor Vessel Integrity Evaluation System) provides four specific integrity evaluation procedures covering PTS(Pressurized Thermal Shock) analysis, P-T(Pressure-Temperature) limit curve generation, USE(Upper Shelf Energy) analysis and Fatigue analysis. Each module was verified by comparing with published results.
- USNRC, 1996, 'Fracture toughnes requirements for protection against pressurized thermal shock events,' 10 CFR 50 50.61
- Harvey, J. F., 1960, Theory and Design of Modern Pressure Vessels, 2nd ed., Van Nostrand Reinhold Co., New Jersey
- Timosenko, S. P., Goodier, J. M., 1970, Theory of Elasticity, 3rd ed., McGrowhill, New York
- 정명조, 박윤원, 이정배, 1997, 'Rancho Seco Transient에 대한 고리 1호기 원자로용기의 건전성 평가,' 대한기계학회논문집(A) 제21권 제7호, pp. 1089-1096
- 곽동옥, 최재붕, 김영진, 표창률, 박윤원, 1999, '가압열충격을 고려한 원자로용기의 건전성 평가를 위한 결정론적 파괴역학 해석,' 대한기계학회논문집(A) 제23권 제8호, pp. 1425-1434
- 김진수, 최재붕, 김영진, 장기상, 최성남, 1999, '원자력발전소 1차계통기기의 결함 안전성 평가 시스템 개발,' 대한기계학회 '99년도 춘계학술대회 논문집 (A), pp. 798-803
- ASME Boiler and Pressure Vessel Code Sec. XI, 1998, 'Fracture Toughness Criteria for Protection Against Failure,' Appendix G.
- EPRI, 1996, 'P-T calculator for Windows version 1.0'
- USNRC, 1988, 'Radiation Embrittlement of Reator Vessel Materials,' Regulatory Guide 1.99, Rev. 2
- ASME Boiler and Pressure Vessel Code Sec. XI, 1998, 'Analysis of Flaw,' Appendix A
- Kim, Y. J., Son, J. H., Chung, H. D. and J. G., 1994, 'Expert System Approach for Reactor Vessel Integrity,' KSME Journal, Vol. 8, No. 2, pp. 198-205
- Strinsnider, J., Wichman, K., Elliot, B., Fairbanks, C., Hackett, E., Sheng, S., Tsao, J., Lois, L., Mayfield, M., Mitchell, M., 1994, Reactor Vassel Status Report, NUREG-1511
- Dickson, T. L., 1994, 'FAVOR: A Fracture Analysis Code for Nuclear Reator Pressure Vessels, Release 9401,' ORNL/NRC/LTR 94-1