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Huh, N. S., Kim, Y.-J. and Kim, Y.-J., 2001, "Application of Enhanced Reference Stress Method to Nuclear Piping LBB Analysis : Finite Element Validation," Trans. of the KSME(A), Vol. 25, No. 4, pp. 741-747.
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Lee, C. Y., Kwon, J. D., Lee, Y. S. and Sul, I. C., 2001, "Application of the Leak Before (LBB) Concept to A Heat Exchanger in A Nuclear Power Plant," KSME International Journal, Vol. 15, No. 1, pp. 10-20.
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3 |
NUREG/CR-6765, 2002, Development of Technical Basis for Leak-Before-Break Evaluation Procedures, Battelle, U.S. NRC.
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NUREG/CR-6873, Vol.2, 2005, The Battelle Integrity of Nuclear Piping (BINP) Program Final Report Appendices, Battelle, U.S. NRC.
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5 |
ASME, 2007, An International Code 2007 Boiler & Pressure Vessel Code, Section II, Part D, Materials
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6 |
Kim, B. S. and Jang, Y. H., 2007, "Reduction of Conservativeness in Thermal Stratification Analysis for LBB Application," Trans. of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 10, 2007.
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Kim, M. W., Kim, Y. J. and Jang, Y. H., 2008, "Level 2 LBB Assessment of A Pressurizer Surgeline in Accordance with NUREG/CR-6765," 2008 Annual Conference of the Korean Society of Pressure Vessels and Piping, pp. 185-186.
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NUREG-0800, 2007, U.S. NRC Standard Review Plan 3.6.3, Revision 1, Leak-Before-Break Evaluation Procedures.
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US NRC Regulatory Guide 1.45, Rev.1, 2008, Guidance on Monitoring and Responding to Reactor Coolant System Leakage.
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NUREG-1061, Vol. 3, 1984, Evaluation of Potential for Pipe Breaks, Report of the U.S. NRC Piping Review Committee.
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10 CFR Part50 App. A, General Design Criteria for Nuclear Power Plants, Rev.4.
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Yu, Y. J. and Kim Y. J., 1996, "Effects of Nozzle on LBB Evaluation for Small Diameter Nuclear Piping," Trans. of the KSME(A), Vol. 20, No. 6, pp. 1872-1881.
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