과제정보
This research was supported by Korea Hydro & Nuclear Power Co., Ltd. (G18IO11).
참고문헌
- U.S. Nuclear Regulatory Commission, Code of Federal Regulations, 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Light Water Nuclear Power Reactors for Normal Operations, 1996.
- M.J. Jhung, S.H. Kim, T.J. Lee, Pressure-temperature limit curve of reactor vessel by ASME code section III and section XI, J. Nucl. Sci. Technol. 33 (2001) 498-513.
- H. Chou, Y. Shen, C. Huang, Development of pressure-temperature operation limits for a PWR vessel considering beltline shell and extended beltline nozzles, Int. J. Pres. Ves. Pip. 179 (2020) 103944. https://doi.org/10.1016/j.ijpvp.2019.103944
- F. Lu, H.Y. Qian, P. Huang, R.S. Wang, Comparison of pressure-temperature limit curves calculation, Proceedings of the ASME Pressure Vessels & Piping Conference PVP2011 (2011) pvp-57449.
- ASME, ASME Boiler and Pressure Vessel Code, Section XI Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix G Fracture toughness criteria for protection against failure, 2017.
- U.S. Nuclear Regulatory Commission, Regulatory Issue Summary 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components, 2014.
- U.S. Nuclear Regulatory Commission, A Survey of Worldwide Experience with the Cracking Susceptibility of Alloy 600 and Associated Welds, 2004.
- U.S. Nuclear Regulatory Commission, NRC Information Notice 2000-17, Supplement 2, Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer, 2001.
- ASME, ASME Boiler and Pressure Vessel Code, Section III Rules for Construction of Nuclear Facility Components, Division 1- Subsection NB, 2017.
- AREVA NP Inc, ANP-10283-NP, Rev.2, U.S. EPR P-T Limits Methodology for RCS Heatup and Cooldown, 2012.
- Dassault Systems, ABAQUS, Version 2019, 2019.
- ASME, ASME Boiler and Pressure Vessel Code, Section II, Part D, 2017. Properties.
- Q. Han, Y. Wang, Y. Yin, D. Wang, Determination of stress intensity factor for mode I fatigue crack based on finite element analysis, Eng. Fract. Mech. 138 (2015) 118-126. https://doi.org/10.1016/j.engfracmech.2015.02.019
- H.D. Kweon, Y.J. Lee, D.H. Kim, D.H. Lee, Evaluation of fracture toughness considering constraint effect of reactor pressure vessel nozzle, KPVP 15 (2019) 71-76.