Investigation on effect of neutron irradiation on welding residual stresses in core shroud of pressurized water reactor
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This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis. First, the welding residual stresses of the core shroud were calculated by applying the heat conduction based lumped pass technique and finite element elastic-plastic stress analysis. Second, the temperature distribution of the core shroud during the normal operation was calculated by performing finite element temperature analysis considering gamma heating. Third, through the finite element viscoelastic-plastic stress analysis using the calculated temperature distribution and setting the calculated residual stresses as the initial stress state, the variation of the welding residual stresses was derived according to repeating the normal operation. In the viscoelastic-plastic stress analysis, the effects of neutron irradiation on mechanical properties during the cyclic normal operations were considered by using the previously developed user subroutines for the irradiation agings such as irradiation hardening/ embrittlement, irradiation-induced creep, and void swelling. Finally, the effect of neutron irradiation on the welding residual stresses was analysed for each irradiation aging. As a result, it is found that as the normal operation is repeated, the welding residual stresses decrease and show insignificant magnitudes after the 10th refueling cycle. In addition, the irradiation-induced creep/void swelling has significant mitigation effect on the residual stresses whereas the irradiation hardening/embrittlement has no effect on those.
Abstract
This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis. First, the welding residual stresses of the core shroud were calculated by applying the heat conduction based lumped pass technique and finite element elastic-plastic stress analysis. Second, the temperature distribution of the core shroud during the normal operation was calculated by performing finite element temperature analysis considering gamma heating. Third, through the finite element viscoelastic-plastic stress analysis using the calculated temperature distribution and setting the calculated residual stresses as the initial stress state, the variation of the welding residual stresses was derived according to repeating the normal operation. In the viscoelastic-plastic stress analysis, the effects of neutron irradiation on mechanical properties during the cyclic normal operations were considered by using the previously developed user subroutines for the irradiation agings such as irradiation hardening/ embrittlement, irradiation-induced creep, and void swelling. Finally, the effect of neutron irradiation on the welding residual stresses was analysed for each irradiation aging. As a result, it is found that as the normal operation is repeated, the welding residual stresses decrease and show insignificant magnitudes after the 10th refueling cycle. In addition, the irradiation-induced creep/void swelling has significant mitigation effect on the residual stresses whereas the irradiation hardening/embrittlement has no effect on those.
참고문헌 (28)
- Generic Aging Lesons Learned (GALL) Report e Final Report, Rev.2, "U. S. NRC", ~, pp.NUREG-1801 (2010)
- Reactor Internal Lifetime Evaluation, Proprietary Class2C, "Westinghouse", ~ (1994)
- Material Reliability Program: Functionality Analysis for Westinghouse and Combustion Engineering Representative PWR Internals, Rev.2, "EPRI", ~, pp.MRP-230 (2012)
- Fitness-For-Service, "API", ~, pp.API 579-1 (2021), ASME FFS-1-2021
- R6: Assessment of the Integrity of Structures Containing Defects, Rev.4, "EDF Energy", ~ (2015)
- Material Reliability Program: Development of Material Constitutive Model for Irradiated Austenitic Stainless Steels, Rev.1, "EPRI", ~, pp.MRP-135 (2010)
- X. Xiao, "Fundamental mechanisms for irradiation-hardening and embrittlement : a review", Metals, 9(10), pp.1132~ (2019)
- Recommended Revision of MRP-135, Irradiated Type 304, "Type 316 Stainless Steel Constitutive, Rev.1", R. S. Dunham, 2006, ANA-06-R-0702
- Material Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data-State of Knowledge, "EPRI", ~, pp.MRP-211 (2007)
- O. K. Chopra, "A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels", J. Nucl. Mater, 409(3), pp.235~356 (2011)
- D. C. Johnson, "Quantitative linkage between the stress at dislocation channel e grain boundary interaction sites and irradiation assisted stress corrosion crack initiation", Acta Mateialia, 170(15), pp.166~175 (2019)
- RPV Internals: Synthesis of Materials Properties under Neutron Irradiation, "J.P. Massoud", EDF, ~, pp.HT-27 (2005), 03[DOI]
- E.R. Gilbert, "The influence of cold-work level on the irradiation creep and swelling of AISI 316 stainless steel irradiated as pressurized tubes in the EBR-II fast reactor", J. Nucl. Mater, 367-370(B), pp.954~958 (2007)
- In-situ NDT measurements of irradiation induced swelling in PWR core internal components, Phase Test. Irradiated Mater, "EPRI", EPRI, 1009762~ (2004)
- A.V. Kozlov, "The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels", Effects of Radiation on Materials: 21st International Symposium (2003), ASTM International
- C. Sun, "Influence of injected interstitials on the void swelling in two structural variants of 304L stainless steel induced by self-ion irradiation at 500 °C", Nucl. Instruments Methods Phys. Res. Sect. B: Beam Interactions Mater. Atoms, 409(15), pp.323~327 (2017)
- R. Pathania, "Analytical and experimental evaluation of residual stresses in BWR core shroud welds", Proc. ASME 1998, PVP-373, Fatigue, Fracture, Residual Stresses (1998), ASME
- J.M. Shim, "Numerical investigation of irradiation induced degradation in a welded core shroud assembly", Int. J. Press. Vessels Piping, 192, pp.104429~ (2021)
- 김종성, "중성자 조사에 따른 오스테나이트 스테인리스 강의 기계적 재료거동 변화를 고려한 사용자 정의 보조 프로그램 개발", 대한기계학회논문집 A, 37(9), pp.1127~1132 (2013), 대한기계학회
- P. Dong, "Recommendations on residual stresses estimate for fitnessfor-service assessment" (2003), welding research Council
- M.C. Smith, "A review of the NeT task group 1 residual stress measurement and analysis round robin on a single weld beadon-plate specimen", Int. J. Press. Vessels Piping, 120-121, pp.93~140 (2014)
- ASME Boiler and Pressure Vessels Code Committee, "ASME B&PV Code, Section II, Part D" (2019), ASME
- KEPCO E&C, "Summary for CMTR of RVI Core Shroud Assembly, TNA59", ~ (2019)
- Dassault Systems, "User's Manual of Simulia: ABAQUS Version 6.19", ~ (2019)
- J.S. Kim, "A study on welding residual stress analysis of a small bore nozzle with dissimilar metal welds", Int. J. Press. Vessels Piping, 90-91, pp.69~76 (2012)
- 김종성, "Investigation on the effects of geometric variables on the residual stresses and PWSCC growth in the RPV BMI penetration nozzles", Journal of Mechanical Science and Technology, 29(3), pp.1049~1064 (2015), 대한기계학회
- Jong-Sung Kim, "Investigation on effect of thermal aging embrittlement on residual stresses of austenitic stainless steel repair welds in nuclear components subject to seismic loads", Journal of Mechanical Science and Technology, 34(7), pp.2821~2831 (2020), 대한기계학회[DOI]
- KEPCO E&C, "Conservative Output for Neutron Flux, Dpa Rate, Gamma Heat Generation of RVI Core Shroud Assembly", ~ (2019)
