Browse > Article
http://dx.doi.org/10.3795/KSME-A.2011.35.6.651

Leak-Before-Break (LBB) Assessment Method Considering Crack Nonlinearity Using Effective Elastic Modulus and Material Nonlinearity  

Kim, Maan-Won (Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.)
Kim, Sung-Hwan (Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.)
Lee, Eui-Jong (Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.35, no.6, 2011 , pp. 651-659 More about this Journal
Abstract
With the increase in the thermal power output of recently developed nuclear power plants, the applied forces and moments are increased in some piping systems, so that the leak-before-break (LBB) application criteria would not be satisfied in those pipes. In this paper, we present a method for obtaining the additive LBB margin in the pipes by considering the nonlinearity of the crack and material properties. Finite element analysis and the moment-rotation equation of beam theory were used to calculate the nonlinearity of the crack and material properties. Moreover crack stability analysis was performed using the method proposed in this study. The LBB margin was increased effectively through consideration of the nonlinearity of the crack and material properties in the pipe.
Keywords
Leak-Before-Break; Crack Stability; Nonlinearity; Effective Elastic Modulus; Finite Element Analysis;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
Times Cited By SCOPUS : 0
연도 인용수 순위
1 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.   과학기술학회마을
2 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.   과학기술학회마을
3 NUREG/CR-6765, 2002, Development of Technical Basis for Leak-Before-Break Evaluation Procedures, Battelle, U.S. NRC.
4 NUREG/CR-6873, Vol.2, 2005, The Battelle Integrity of Nuclear Piping (BINP) Program Final Report Appendices, Battelle, U.S. NRC.
5 ASME, 2007, An International Code 2007 Boiler & Pressure Vessel Code, Section II, Part D, Materials
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.
7 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.
8 NUREG-0800, 2007, U.S. NRC Standard Review Plan 3.6.3, Revision 1, Leak-Before-Break Evaluation Procedures.
9 US NRC Regulatory Guide 1.45, Rev.1, 2008, Guidance on Monitoring and Responding to Reactor Coolant System Leakage.
10 NUREG-1061, Vol. 3, 1984, Evaluation of Potential for Pipe Breaks, Report of the U.S. NRC Piping Review Committee.
11 10 CFR Part50 App. A, General Design Criteria for Nuclear Power Plants, Rev.4.
12 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.   과학기술학회마을