Acknowledgement
This research was partly supported by a National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIP: Ministry of Science, ICT and Future Planning) (No. NRF-2017M2B2B1072552) and by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) funded by the financial resource granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 1305008).
References
- Khnp, Hanuel 3,4 Final Safety Analysis Report, 1998.
- S. Israel, EPR: Steam Generator Tube Rupture Analysis in Finland and in France, Technical Report, IRSN, 2006.
- P. MacDonald, V. Shah, L. Ward, P. Ellison, NUREG/CR-6365, Steam Generator Tube Failures, 1996.
- KINS, Evaluation of Thermal-hydraulic Behavior Following the Steam Generator Tube Rupture Event of Ulchin Unit 4, KINS/ER-056, 2003.
- U. Nrc, Shutdown and Low Power Operation at Commercial Nuclear Power in the United States, NUREG-1449, US NRC, 1993.
- M. Barriere, W. Luckas, D. Whitehead, A. Ramey-Smith, An Analysis of Operational Experience during Low Power and Shutdown and a Plan for Addressing Human Reliability Assessment Issues, Nuclear Regulatory Commission, 1994.
- W. Werner, M. Hirano, S. Kondo, G. Johanson, J. Lanore, J. Murphy, U. Schmocker, Results and insights from level-1 probabilistic safety assessments for nuclear power plants in France, Germany, Japan, Sweden, Switzerland and the United States, Reliab. Eng. Syst. Saf. 48 (3) (1995) 165-179. https://doi.org/10.1016/0951-8320(95)00016-U
- T. Chu, Z. Musicki, P. Kohut, J. Yang, G. Bozoki, C. Hsu, D. Diamond, D. Bley, D. Johnson, B. Holmes, Evaluation of Potential Severe Accidents during Low Power and Shutdown Operations at Surry, Unit-1: Analysis of Core Damage Frequency from Internal Events during Mid-loop Operations. Appendix I, Volume 2, Part 5, Nuclear Regulatory Commission, Office of, Washington, DC (United States), 1994.
- I. Low-Power, S.O. MODES, Unclassified NEA/CSNI/R (97) 17, 1998.
- J.H. Jeong, K.Y. Choi, Effects of tube rupture modeling and the parameters on the analysis of multiple steam generator tube rupture event progression in APR1400, Nucl. Eng. Des. 224 (3) (2003) 313-336. https://doi.org/10.1016/S0029-5493(03)00132-8
- U. Nrc, SECY-93-087,", policy, technical, and licensing issues pertaining to evolutionary and advanced light-water (ALWR) designs, issued April (1993) 2.
- C.-K. Lim, S.-K. Han, S.-K. Kim, D.-S. Jin, B.-J. Ko, Y.-H. Hong, K.-I. Ahn, S.-Y. Park, S.-W. Hwang, P. McMinn, Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code, Nucl. Eng. Des. 359 (2020) 110452. https://doi.org/10.1016/j.nucengdes.2019.110452
- B.D. Chung, K.D. Kim, S.W. Bae, J.J. Jeong, S.W. Lee, M.K. Hwang, C. Yoon, MARS Code Manual Volume I: Code Structure, System Models, and Solution Methods, Korea Atomic Energy Research Institute, 2010.
- W.-J. Lee, D.-W. Jerng, S.S. Jeon, S.J. Hong, Characteristics analysis of SGTR accidents under the shutdown conditions, Transactions 115 (1) (2016) 885-887.
- E.H. Lee, W.J. Lee, J.J. Bang, D.W. Jerng, H.A. Sang Jun, Comparison of SGTR accident under full-power and shutdown conditions, in: 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH, 2017, 2017.
- Y.-S. Son, J.-Y. Shin, H.-G. Lim, J.-H. Park, S.-C. Jang, Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR, Nucl. Eng. Des. 235 (15) (2005) 1571-1581. https://doi.org/10.1016/j.nucengdes.2005.01.012
- A.P.R. Khnp, 1400 Standard Safety Analysis Report Chapter 5, 2002.
- V. Ben cik, D. Grgic, N. Cavlina, Analysis of steam generator tube rupture(SGTR) accident for NPP Krsko, in: International Conference Nuclear Energy for New Europe, 2012.
- T. Takeda, ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions, Nuclear Engineering and Technology 50 (6) (2018) 981-988. https://doi.org/10.1016/j.net.2018.05.002
- I.A.E. Agency, Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants, IAEA, 2016.
- R. Tregoning, L. Albramson, P. Scott, Estimating Loss-Of-Coolant Accident (LOCA) Frequencies through the Elicitation Process, United States Nuclear Regulatory Commission, Office of Nuclear Regulatory, 2008.
- N.R. Commission, NRC Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity, NUREG-0844, Nuclear Regulatory Commission, US, 1988.
- K.W. Seul, Y.S. Bang, I.G. Kim, T. Yonomoto, Y. Anoda, Simulation of multiple steam generator tube rupture (SGTR) event scenario, Nuclear Engineering and Technology 35 (3) (2003) 179-190.