참고문헌
- U.S.NRC, Generic Aging Lesons Learned (GALL) Report - Final Report, NUREG1801, Rev.2, 2010.
- Westinghouse, Reactor Internal Lifetime Evaluation, Proprietary Class2C, 1994.
- EPRI, Material Reliability Program: Functionality Analysis for Westinghouse and Combustion Engineering Representative PWR Internals, MRP-230, Rev.2, 2012.
- API and ASME, Fitness-For-Service, API 579-1/ASME FFS-1-2021, 2021.
- EDF Energy, R6: Assessment of the Integrity of Structures Containing Defects, Rev.4, 2015.
- EPRI, Material Reliability Program: Development of Material Constitutive Model for Irradiated Austenitic Stainless Steels, MRP-135, Rev.1, 2010.
- X. Xiao, Fundamental mechanisms for irradiation-hardening and embrittle-ment: a review, Metals 9 (10) (2019) 1132.
- R.S. Dunham, Y.R. Rashid, Recommended Revision of MRP-135, Irradiated Type 304/Type 316 Stainless Steel Constitutive Model, ANA-06-R-0702, Rev.1, 2006.
- EPRI, Material Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data-State of Knowledge, MRP-211, 2007.
- O.K. Chopra, A.S. Rao, 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) (2011) 235-356. https://doi.org/10.1016/j.jnucmat.2010.12.001
- D.C. Johnson, B. Kuhr, D. Farkas, G.S. Was, Quantitative linkage between the stress at dislocation channel - grain boundary interaction sites and irradiation assisted stress corrosion crack initiation, Acta Mateialia 170 (15) (2019) 166-175. https://doi.org/10.1016/j.actamat.2019.02.032
- J.P. Massoud, RPV Internals: Synthesis of Materials Properties under Neutron Irradiation, HT-27/03/028/A, EDF, 2005.
- E.R. Gilbert, F.A. Garner, 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) (2007) 954-958. https://doi.org/10.1016/j.jnucmat.2007.03.059
- EPRI, In-situ NDT measurements of irradiation induced swelling in PWR core internal components, Phase Test. Irradiated Mater. EPRI Rep. (2004), 1009762.
- A.V. Kozlov, E.N. Shcherbakov, S.A. Averin, F.A. Garner, in: M.L. Grossbeck (Ed.), The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels," Effects of Radiation on Materials: 21st International Symposium, ASTM STP 1447, ASTM International, West Conshohocken, PA, 2003.
- C. Sun, F.A. Garner, L. Shao, X. Zhang, S.A. Maloy, Influence of injected in-terstitials on the void swelling in two structural variants of 304L stainless steel induced by self-ion irradiation at 500 ℃, Nucl. Instruments Methods Phys. Res. Sect. B: Beam Interactions Mater. Atoms 409 (15) (2017) 323-327. https://doi.org/10.1016/j.nimb.2017.03.070
- R. Pathania, W. Cheng, M. Kreider, N. Cofie, J. Brihmadesam, Analytical and experimental evaluation of residual stresses in BWR core shroud welds, Proc. ASME 1998, PVP-373, Fatigue, Fracture, Residual Stresses, ASME (1998).
- J.M. Shim, Y.S. Chang, M.W. Kim, J.S. Yang, Numerical investigation of irradiation induced degradation in a welded core shroud assembly, Int. J. Press. Vessels Piping 192 (2021), 104429.
- J.S. Kim, M.J. Jhung, J.S. Park, Development of user subroutine program considering effect of neutron irradiation on mechanical material behavior of austenitic stainless steels, Trans. Korean Soc. Mech. Eng. A 37 (9) (2013) 1127-1132. https://doi.org/10.3795/KSME-A.2013.37.9.1127
- P. Dong, J.K. Hong, Recommendations on residual stresses estimate for fitness-for-service assessment, welding research Council, WRC Bull. 476 (2003).
- M.C. Smith, A.C. Smith, R.C. Wimpory, A review of the NeT task group 1 residual stress measurement and analysis round robin on a single weld bead-on-plate specimen, Int. J. Press. Vessels Piping 120-121 (2014) 93-140. https://doi.org/10.1016/j.ijpvp.2014.05.002
- ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section II, Part D, ASME, New York, 2019.
- 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, J.H. Seo, A study on welding residual stress analysis of a small bore nozzle with dissimilar metal welds, Int. J. Press. Vessels Piping 90-91 (2012) 69-76. https://doi.org/10.1016/j.ijpvp.2011.10.010
- J.S. Kim, M.S. Ra, K.S. Lee, Investigation on the effects of geometric variables on the residual stresses and PWSCC growth in the RPV BMI penetration nozzles, J. Mech. Sci. Tech. 29 (3) (2015) 1049e1064.
- J.S. Kim, M.W. Kim, J.S. Yang, Investigation on effect of thermal aging embrittlement on residual stresses of austenitic stainless steel repair welds in nuclear components subject to seismic loads, J. Mech. Sci. Tech. 34 (7) (2020) 2821-2831. https://doi.org/10.1007/s12206-020-0615-4
- KEPCO E&C, Conservative Output for Neutron Flux, Dpa Rate, Gamma Heat Generation of RVI Core Shroud Assembly, 2019.