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http://dx.doi.org/10.5516/NET.2010.42.5.590

FATIGUE LIFE ASSESSMENT OF REACTOR COOLANT SYSTEM COMPONENTS BY USING TRANSFER FUNCTIONS OF INTEGRATED FE MODEL  

Choi, Shin-Beom (School of Mechanical Engineering, Sungkyunkwan University)
Chang, Yoon-Suk (Department of Nuclear Engineering, Kyung Hee University)
Choi, Jae-Boong (School of Mechanical Engineering, Sungkyunkwan University)
Kim, Young-Jin (School of Mechanical Engineering, Sungkyunkwan University)
Jhung, Myung-Jo (Korea Institute of Nuclear Safety)
Choi, Young-Hwan (Korea Institute of Nuclear Safety)
Publication Information
Nuclear Engineering and Technology / v.42, no.5, 2010 , pp. 590-599 More about this Journal
Abstract
Recently, efficient operation and practical management of power plants have become important issues in the nuclear industry. In particular, typical aging parameters such as stress and cumulative usage factor should be determined accurately for continued operation of a nuclear power plant beyond design life. However, most of the major components have been designed via conservative codes based on a 2-D concept, which do not take into account exact boundary conditions and asymmetric geometries. The present paper aims to suggest an effective fatigue evaluation methodology that uses a prototype of the integrated model and its transfer functions. The validity of the integrated 3-D Finite Element (FE) model was proven by comparing the analysis results of individual FE models. Also, mechanical and thermal transfer functions, known as Green's functions, were developed for the integrated model with the standard step input. Finally, the stresses estimated from the transfer functions were compared with those obtained from detailed 3-D FE analyses results at critical locations of the major components. The usefulness of the proposed fatigue evaluation methodology can be maximized by combining it with an on-line monitoring system, and this combination, will enhance the continued operations of old nuclear power plants.
Keywords
Continued Operation; Finite Element Method; Integrated Model; On-line Monitoring System; Transfer Functions;
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1 F. Bazile, C. Braun, C. R. Clark, M. Condu, K. Dahlgren Persson, R. I. Facer, R. Friedrich, J. Georgiev, R. Hagen, G. Hopton, L. Langlois, M. Laraia, P. Louis, A. Omoto, N. Pieroni, A. Pryakhin, H. H. Rogner, J. Vilemas and D. J. Wilson, “Consideration of Early Closure or Continued Operation of a Nuclear Power Plant,” IAEA-TECDOC-1514, International Atomic Energy Agency (2006).
2 G. H. Koo, J. J. Kwon and W. J. Kim, “Green’s Function Method with Consideration of Temperature Dependant Material Properties for Fatigue Monitoring of Nuclear Power Plants,” International Journal of Pressure Vessels and Piping, 86, 187-195 (2009).   DOI
3 Sungkyunkwan University, “Study on Integrity Evaluation for Pressurized Components in Nuclear Power Plant,” KINS/HR-772, Korea Institute of Nuclear Safety (2007).
4 ANSYS, “Introduction of ANSYS Ver.11,” ANSYS Inc. (2008).
5 S. B. Choi, Y. S. Chang, J. B. Choi, Young-Jin Kim, M. J. Jhung, Y. H. Choi and T. E. Jin, “Comparative Stress Analyses of Major RCPB Components by Using a Prototype of Integrated Finite Element Model,” 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT20), Espoo, Finland, August 9-14, 2009.
6 J. B. Choi, S. W. Yeom, H. O. Ko, Y. J. Kim, H. K. Kim, Y. H. Choi and Y. W. Park, “Development of a Web-Based Aging Monitoring System for the Integrity Evaluation of Major Components in a Nuclear Power Plant,” Proceedings of the 7th International Workshop on the Integrity of Nuclear Components (ASINCO7), Muju, Korea, July 3-4, 2008.
7 Sungkyunkwan University, “Development of Web-Based Aging Evaluation Code and Web Design of Aging Monitor for Standard Nuclear Power Plant,” KINS/HR-877, Korea Institute of Nuclear Safety (2008).
8 M. Brumovsky, B. Elliot, C. Faidy, T. Inagaki, K. S. Kang, B. Kastner, T. R. Mager, Y. Makihara, J. Pachner, A. Plyushch and V. A. Piminov, “Assessment and Management of Aging of Major Nuclear Power Plant Components Important to Safety: PWR Pressure Vessels,” IAEATECDOC-1120, International Atomic Energy Agency (1999).
9 R. C. Hibbler, Mechanics of Materials, 4th ed., 409-412, Prentice Hall Inc., Upper Saddle River, New Jersey (2000).
10 A. G. Miller, B. Kaufer and L. Carlsson, “Activities on component reliability under the OECD Nuclear Energy Agency,” Nuclear Engineering Design, 198, 325-334 (2000).   DOI
11 J. A. Bannantine, J. J. Corner and J. L. Handrock, Fundamentals of Metal Fatigue Analysis, Prentice Hall Inc., Upper Saddle River, New Jersey (1990).
12 S. P. Timoshenko and J. N. Goodier, Theory of Elasticity, 3rd ed., McGraw-Hill International Editions, p. 68-71, 1221 Ave. of the Americas, New York (1982).
13 P. Aufort, G. Bimont, T. H. Chau, I. Fournier, P. Morilhat, T. Souchois and G. Codrdier, “On Line Fatiguemeter: a Large Experiment in French Nuclear Plants,” Nuclear Engineering and Design, 129, 177-184 (1991).   DOI
14 Nuclear District Heating Reactor Development Department, “Development of Operating Transients Monitoring System for Primary Components of Nuclear Power Plants,” KAERI/RR-1080/91, Korea Atomic Energy Research Institute (1991).
15 S. Crutzen and P. Jehenson, “Inspection Performance with a View to Pressure Vessel Life Management,” International Journal of Pressure Vessels and Piping, 54, 107-136 (1993).   DOI
16 P. C. Riccardella, A. Y. Kuo, S. S. Tang and H. L. Gustin, “FatiguePro: On-Line Fatigue Usage Transient Monitoring System,” EPRI NP-5835M, Electric Power Research Institute (1988).
17 B. Yoo, “Development of Fatigue Monitoring System in Nuclear Power Plants,” KAERI/RR-1307/93, Korea Atomic Energy Research Institute (1994).
18 J. C. Kim, M. Y. Ahn, Y. S. Chang, J. B. Choi, Y. J. Kim, M. J. Jhung and Y. H. Choi, “Fatigue Life Evaluation for Nuclear Power Plant using Green’s Function and Real Operating Histories,” Key Engineering Materials, 326-328, 979-982 (2006).   DOI
19 Y. S. Chang, S. B. Choi, J. B. Choi, Y. J. Kim, M. J. Jhung and Y. H. Choi, “Formulation of Three-Dimensional Green’s Function and Its Application to Fatigue Life Evaluation of Pressurizer,” Key Engineering Materials, 324-325, 397-390 (2006).
20 S. B. Choi, S. W. Woo, Y. S. Chang, J. B. Choi, Y. J. Kim, M. J. Jhung and Y. H. Choi, “Development of Green Functions of Steam Generator Shells using Real Operating Data,” Transaction of the Korean Nuclear Society Autumn Meeting, Pyeonchang, Korea, Oct. 25-26, 2007.