Acknowledgement
This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2106007). The authors also would like to thank the reviewers for giving very detailed and useful reviews to strengthen the paper.
References
- B.R. Sehgal, et al., Nuclear Safety in Light Water Reactor - Severe Accident Phenomenology, Elsevier, Oxford, UK, 2012.
- W.B. Scott, et al., Recriticality in a BWR Following a Core Damage Event, NUREG/CR-5653, U.S. NRC, Washington, D.C, 1990.
- W. Frid, et al., Severe Accident, Recriticality Analyses (SARA), Swedish Nuclear Power Inspectorate, Stockholm, Sweden, 1999.
- Fauke, L.L.C. Associates, MAAP5 Modular Accident Analysis Program, Electric Power Research Institute (EPRI), Palo Alto, CA, 2008.
- J. Leppanen, The Serpent Monte Carlo code : status, development and application in 2013, Ann. Nucl. Energy 82 (2015) 142-150. https://doi.org/10.1016/j.anucene.2014.08.024
- F.J. Rahn, et al., Technical Evaluation of Fukushima Accidents Phase 2 - Potential for Recriticality during Degraded Core Reflood, Electric Power Research Institute (EPRI), Palo Alto, CA, 2016.
- P. Darnowski, et al., Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident, Ann. Nucl. Energy 99 (2017) 495-509. https://doi.org/10.1016/j.anucene.2016.10.004
- R.O. Gauntt, et al., MELCOR Computer Code Manuals Vol. 1 : Primer and Users' Guide, Version 1.8.6, Sandia National Laboratories, Albuquerque, NM, 2005.
- Y. Lee, et al., Whole-core analyses on recriticality of conventional high power pressurized water reactor in Korea during early phase of severe accident, Ann. Nucl. Energy 143 (2020), 107461.
- U. S. NRC, 10CFR 72.124, Criteria for nuclear criticality safety, Washington, DC, 1988.
- M. Barrachin, et al., Late phase fuel degradation in the Phebus FP tests, Ann. Nucl. Energy 61 (2013) 36-53. https://doi.org/10.1016/j.anucene.2013.03.041
- A. Seibert, et al., Thermophysical properties of U, Zr-oxides as prototypic corium materials, J. Nucl. Mater. 520 (2019) 165-177. https://doi.org/10.1016/j.jnucmat.2019.04.019
- M. Salam, C.J. Hah, Comparative study on nuclear characteristics of APR1400 between 100% MOX core and UO2 core, Ann. Nucl. Energy 119 (2018) 374-381. https://doi.org/10.1016/j.anucene.2018.05.008
- B. Cho, et al., User's Manual for the Rectangular Three-Dimensional Diffusion Nodal Code COREDAX-2 Version 1.0, KINS/HR-1355, NURAPT-2014-01, Korea Institute of Nuclear Safety (KINS), Korea Advanced Institute of Science and Technology (KAIST) Daejeon, Korea, 2011 (In Korean).
- R.M. Erick, R.A. Sallach, Fission Product Chemistry in the Primary System, Proc. Int'l. Mtg. On LWR Severe Accident Evaluation, 1983 (Cambridge. MA).
- D.A. Powers, J.E. Brockmann, A.W. Shiver, VANESA: A Mechanistic Model of Radionuclide Release and Aerosol Generation during Core Debris Interactions with Concrete, NUREC/CR-4308, SAND85-1370, Sandia National Laboratories, Albuquerque, NM, 1986.
- O. De Luze, Degradation and oxidation of B4C control rod segments at high temperatures. A review and code interpretation of the BECARRE program, Nucl. Eng. Des. 259 (2013) 150-165. https://doi.org/10.1016/j.nucengdes.2013.02.038
- T. Haste, et al., Study of boron behavior in the primary circuit of water reactors under severe accident conditions: a comparison of Phebus FPT3 results with other recent integral and separate-effect data, Nucl. Eng. Des. 246 (2012) 147-156. https://doi.org/10.1016/j.nucengdes.2011.08.031
- G. Repetto, et al., B4C oxidation modelling in severe accident codes: applications to PHEBUS and QUENCH experiments, Ann. Nucl. Energy 52 (2010) 37-45. https://doi.org/10.1016/j.pnucene.2009.09.017
- M. Steinbruck, Influence of boron carbide on core degradation during severe accidents in LWRs, Ann. Nucl. Energy 64 (2014) 43-49. https://doi.org/10.1016/j.anucene.2013.09.027