Acknowledgement
This study was supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea (No. 1805003).
References
- International Atomic Energy Agency, The Fukushima Daiichi Accident, IAEA, Vienna, Pub-1710, 2015.
- Organisation for Economic Co-operation and Development, Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt, OECD NEA, 2016. No. 7284.
- M. Cherubini, N. Muellner, F. D'auria, G. Petrangeli, Application of an optimized AM procedure following a SBO in a VVER-1000, Nucl. Eng. Des. 238 (2008) 74-80, https://doi.org/10.1016/j.nucengdes.2007.04.016.
- Y.P. Zhang, W.X. Tian, S.Z. Qiu, G.H. Su, Transient analyses of station blackout accident for CPR1000, At. Energy Sci. Technol. 45 (2011) 1056-1059.
- C.W. Huh, N. Suh, G.-C. Park, Optimum RCS depressurization strategy for effective severe accident management of station black out accident, Nucl. Eng. Des. 239 (2009) 2521-2529, https://doi.org/10.1016/j.nucengdes.2009.07.028.
- B. Chatterjee, P. Mukhopadhyay, H.G. Lele, A.K. Ghosh, H.S. Kushwaha, P. Groudev, B. Atanasova, Analyses for VVER-1000/320 reactor for spectrum of break sizes along with SBO, Ann. Nucl. Energy 37 (2010) 359-370, https://doi.org/10.1016/j.anucene.2009.12.005.
- B.P. Atanasova, A.E. Stefanova, P.P. Groudev, VVER 1000 SBO calculations with pressuriser relief valve stuck open with ASTEC computer code, Ann. Nucl. Energy 46 (2012) 121-127, https://doi.org/10.1016/j.anucene.2011.12.024.
- S.Y. Park, G.I. Ahn, Comparative analysis of station blackout accident progression in typical PWR, BWR, and PHWR, Nucl. Eng. Technol. 44 (2012) 311-322, https://doi.org/10.5516/NET.03.2011.046.
- T. Nitheanandan, M.J. Brown, Backup and ultimate heat sinks in CANDU reactors for prolonged SBO accidents, Nucl. Eng. Technol 45 (2013) 589-596, https://doi.org/10.5516/NET.03.2013.711.
- E. Dinca, D. Dupleac, I. Prisecaru, Verification by analytical means of the efficiency of some accident management measures for SBO at a CANDU-6 NPP, International Nuclear Safety Journal 4 (2015) 9-22.
- F. Zhou, D.R. Novog, RELAP5 simulation of CANDU station blackout accidents with/without water make-up to the steam generators, Nucl. Eng. Des. 318 (2017) 35-53, https://doi.org/10.1016/j.nucengdes.2017.04.014.
- P.J. Ingham, J.C. Luxat, A.J. Melnyk, T.V. Sanderson, Natural Circulation in an Integral CANDU Test Facility, IAEA, 2000, pp. 201-212. TECDOC-1149.
- Korea Institute of Nuclear Safety, MARS-KS Code Manual, KINS, 2018. KINS/RR-1822.
- Korea Hydro & Nuclear Power Co., Ltd., Final Safety Assessment Report of Wolsong 3/4 Units, KHNP, 2019.