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http://dx.doi.org/10.1016/j.net.2021.11.022

Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors  

Kim, Jong-Sung (Department of Nuclear Engineering, Sejong University Seoul)
Seo, Jun-Min (Department of Mechanical Engineering, Graduate School, Korea University Seoul)
Kang, Ju-Yeon (Dassault Systemes Korea Corporation)
Jang, Youn-Young (Dept. of Mech. System Design Engineering, Seoul National University of Science and Technology)
Lee, Yun-Joo (Korea Electric Power Company Engineering & Construction)
Kim, Kyu-Wan (Korea Electric Power Company Engineering & Construction)
Publication Information
Nuclear Engineering and Technology / v.54, no.5, 2022 , pp. 1726-1746 More about this Journal
Abstract
This paper presents fracture mechanics analysis results for various cracks located at pressurized water reactor pressure vessel nozzle crotch corners taking into consideration constraint effect. Technical documents such as the ASME B&PV Code, Sec.XI were reviewed and then a fracture mechanics analysis procedure was proposed for structural integrity assessment of various nozzle crotch corner cracks under normal operation conditions considering the constraint effect. Linear elastic fracture mechanics analysis was performed by conducting finite element analysis with the proposed analysis procedure. Based on the evaluation results, elastic-plastic fracture mechanics analysis taking into account the constraint effect was performed only for the axial surface crack of the reactor pressure vessel outlet nozzle with cladding. The fracture mechanics analysis result shows that only the axial surface crack in the reactor pressure vessel outlet nozzle has the stress intensity factor exceeding the low bound of upper-shelf fracture toughness irrespectively of considering the constraint effect. It is confirmed that the J-integral for the axial crack of the outlet nozzle does not exceed the ductile crack initiation toughness. Hence, it can be ensured that the structural integrity of all the cracks is maintained during the normal operation.
Keywords
Fracture mechanics; Constraint effect; Reactor pressure vessel; Nozzle crotch corner; P-T limit; Upper-shelf fracture toughness; Finite element analysis;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
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1 S. Yin, G.L. Stevens, B.R. Bass, M.T. Kirk, Stress and fracture mechanics analysis of boiling water reactor and pressurized water reactor pressure vessel nozzles, Proceedings of ASME PVP (2011) PVP2011-57014, 2011.
2 F. Horokawa, M. Hayashi, M. Masuda, Y. Mabuchi, Y. Yamamoto, F. Iwamatsu, K. Miyazaki, D. Johnson, Defect tolerance assessment for ABWR nozzle crotch corner, Proceedings of ASME PVP (2016) PVP2016, 63823 (2016).
3 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix A: Analysis of Flaws, ASME, New York, 2019, 2019.
4 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Code Case N-629: Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials, ASME, New York, 1999.
5 US NRC, Regulatory Guide 1.154: Format and Content of Plant-specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors, 1987.
6 P. Vladislav, M. Pota, D. Lauerova, Probabilistic assessment of pressurized thermal shock, Nucl. Eng. Des. 272 (2013) 84-91.   DOI
7 D. Siegele, I. Varfolomeev, G. Nagel, Constraint based assessment of postulated nozzle corner cracks, Proceedings of ASME PVP (2002) PVP2002, 1352 (2002).
8 British Energy, Assessment of the Integrity of Structures Containing Defects. British Energy Generation Report R6 Revision, 4, Gloucester, 2001.
9 K. Wallin, Irradiation damage effects on the fracture toughness transition curve shape for reactor pressure vessel steels, Int. J. Pres. Ves. Pip. 55 (1993) 61-79.   DOI
10 M. EricksonKirk, M. EricksonKirk, An upper-shelf fracture toughness master curve for ferritic steels, Int. J. Pres. Ves. Pip. 83 (2006) 571-583.   DOI
11 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section III, Code Case N-830-1: Direct Use of Fracture Toughness for Flaw Evaluation of Pressure Boundary Materials in Class 1 Ferritic Steel Components, ASME, New York, 2020.
12 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section II, Part D: Properties. 2019, ASME, New York, 2019.
13 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section III, Code Case N-631: Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials Other than Bolting for Class 1 Vessels, ASME, New York, 1999.
14 Oak Ridge National Laboratory, Fracture Analysis of Vessels-Oak Ridge FAVOR, V06.1, Computer Code: Theory and Implementation of Algorithms, Methods and Correlations, Oak Ridge National Laboratory, Washington, D.C., 2006.
15 M. EricksonKirk, M. EricksonKirk, The relationship between the transition and upper-shelf fracture toughness of ferritic steels, Fatig. Fract. Eng. Mater. Struct. 29 (2006) 672-684.   DOI
16 M. Kirk, M. Erickson, W. Server, G. Stevens, R. Cipolla, Assessment of fracture toughness models for ferritic steels used in Section XI of the ASME Code relative to current data-based models, Proceedings of ASME PVP (2014) PVP2014, 28540 (2014).
17 K. Wallin, Quantifying Tstress controlled constraint by the master curve transition temperature T0, Eng. Fract. Mech. 68 (2001) 303-328.   DOI
18 Dassault Systems, User's manual of Simulia, 2019. ABAQUS Version 6.19.
19 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section III, Nonmandatory Appendices, Appendix G: Fracture Toughness Criteria for Protection against Failure, ASME, New York, 2019, 2019.
20 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix E: Evaluation of Unanticipated Operating Events, ASME, New York, 2019, 2019.
21 K.S. Lee, S.H. Lee, J.W. Kim, A study for experiment to measure mechanical properties of pressurizer nozzle and safety-ends in nuclear power plant, Journal of the Korean Society for Nondestructive Journal of the Korean Society Nondestructive Testing 33 (2) (2013) 147-153.   DOI
22 R.K. Blandford, D.K. Morton, S.D. Snow, T.E. Rahl, Tensile stress-strain results for 304L and 316L stainless steel plate at temperature, Proceedings of ASME PVP (2007) PVP2007-26096, 2007.
23 E.&C. KEPCO, KHNP. Design Specification of APR 1400, 2018.
24 W.E. Pennell, Structural integrity assessment of aging nuclear reactor pressure vessels, Nucl. Eng. Des. 172 (1997) 27-47.   DOI
25 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix G: Fracture Toughness Criteria for Protection against Failure, ASME, New York, 2019, 2019.
26 ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix K: Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact Energy Levels, ASME, New York, 2019, 2019.
27 US NRC, 10 CFR 50.61, Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events, 2006.
28 S. Choi, H.B. Surh, J.W. Kim, Effect of postulated crack location on the pressuretemperature limit curve of reactor pressure vessel, Nuclear Eng. Technol. 51 (2019) 1681-1688.   DOI
29 M. Chen, G. Qian, J. Shi, R. Wang, W. Yu, F. Lu, G. Zhang, F. Xue, Z. Chen, Application of the French Codes to the pressurized thermal shock assessment, Nuclear Eng. Technol. 48 (2016) 1423-1432.   DOI
30 Welding Research Council, PVRC Recommendations on Toughness Requirements for Ferritic Materials, 1972.