Transient heat transfer analysis of double-layer molten pool under severe accident

References

• Jung G, Jae M. Quantitative assessment of severe accident management strategies in a nuclear power plant. J Nucl Sci Technol. 2018;55:691–702.
   Web of Science ®Google Scholar
• Kang S, Park SD, Kim IG, et al. Numerical study of in-vessel retention under the gallium–water external reactor vessel cooling system using MARS-LMR. J Nucl Sci Technol. 2015;53:345–352.
   Web of Science ®Google Scholar
• Kymäläinen O, Tuomisto H, Theofanous T. In-vessel retention of corium at the Loviisa plant. Nucl Eng Des. 1997;169:109–130.
   Web of Science ®Google Scholar
• Talbott EO, Youk AO, McHugh KP, et al. Mortality among the residents of the Three Mile Island accident area: 1979–1992. Environ Health Perspect. 2000;108:545–552.
   PubMed Web of Science ®Google Scholar
• Walsh EJ, Warland RH. Social movement involvement in the wake of a nuclear accident: activists and free riders in the TMI area. Am Sociological Rev. 1983;48:764–780.
   Web of Science ®Google Scholar
• Zhang L, Zhou Y, Zhang Y, et al. Natural convection heat transfer in corium pools: a review work of experimental studies. Prog Nucl Energy. 2015;79:167–181.
   Web of Science ®Google Scholar
• Wang K, Erkan N, Gong H, et al. Comparison of pool boiling CHF of a polished copper block and carbon steel block on a declined slope. J Nucl Sci Technol. 2018;55:1065–1078.
   Web of Science ®Google Scholar
• Ming Y, Saeed Ahmad A. Review of severe accident phenomena in LWR and related severe accident analysis codes. Res J Appl Sci Eng Technol. 2013;5:3320–3335.
   Google Scholar
• Tran C-T, Dinh T-N. The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: physical processes, modeling and model implementation. Prog Nucl Energy. 2009;51:849–859.
   Web of Science ®Google Scholar
• Tran C-T, Dinh T-N. The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: model assessment and application. Prog Nucl Energy. 2009;51:860–871.
   Web of Science ®Google Scholar
• Zhang L, Zhang Y, Zhao B, et al. COPRA: a large scale experiment on natural convection heat transfer in corium pools with internal heating. Prog Nucl Energy. 2016;86:132–140.
   Web of Science ®Google Scholar
• Zhang YP, Su GH, Qiu SZ, et al. Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process. Prog Nucl Energy. 2014;74:213–221.
   Web of Science ®Google Scholar
• Wei H, Chen Y-T. Numerical investigation of geometric size effect on the internal heated water pool natural convection behavior. Prog Nucl Energy. 2019;112:34–50.
   Web of Science ®Google Scholar
• Bonnet J. Thermal hydraulic phenomena in corium pools: the BALI experiment. Japan Atomic Energy Research Inst. Tokyo (Japan); 1999: JAERI-Conf-99-005.
   Google Scholar
• Bonnet JM. Thermal hydraulic phenomena in corium pools for ex-vessel situations: the BALI experiment. Germany; 2000. ( no. 0947-8620).
   Google Scholar
• Zhang L, Luo S, Zhang Y, et al. Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools. Ann Nucl Energy. 2018;111:293–302.
   Web of Science ®Google Scholar
• Luo S, Zhang Y, Zhou Y, et al. COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt. Appl Therm Eng. 2018;140:313–324.
   Web of Science ®Google Scholar
• Zhang L, Zhou Y, Luo S, et al. Large eddy simulation for the thermal behavior of one-layer and two-layer corium pool configurations in HPR1000 reactor. Appl Therm Eng. 2018;145:38–47.
   Web of Science ®Google Scholar
• Lee -J-J, Yoon S-J, Park G-C, et al. Turbulence-induced heat transfer in PBMR core using LES and RANS. J Nucl Sci Technol. 2007;44:985–996.
   Web of Science ®Google Scholar
• Park J-W, Song H-J. Numerical computation of a reactor vessel melting under external cooling conditions. J Nucl Sci Technol. 2017;54:694–704.
   Web of Science ®Google Scholar
• Jofre L, Dodd MS, Grau J, et al. Near-interface flow modeling in large-eddy simulation of two-phase turbulence. Int J Multiphase Flow. 2020;132:103406.
   Web of Science ®Google Scholar
• Ge X, Vasilyev OV, Hussaini MY. Wavelet-based adaptive wall-modeled large eddy simulation method for compressible turbulent flows. Phys Rev Fluids. 2021;6:094606.
   Web of Science ®Google Scholar
• Wei H, and Chen Y-T. Numerical investigation of the internally heated melt pool natural convection behavior with the consideration of different high internal Rayleigh numbers. Annals of Nuclear Energy. 2020;143:107427.
   Web of Science ®Google Scholar
• Bechta SV, Granovsky VS, Khabensky VB, et al. Corium phase equilibria based on MASCA, METCOR and CORPHAD results. Nucl Eng Des. 2008;238:2761–2771.
   Web of Science ®Google Scholar
• Fukasawa M, Tamura S, Hasebe M. Development of thermodynamic database for U—Zr—Fe—O—B—C—FPs system. J Nucl Sci Technol. 2005;42:706–716.
   Web of Science ®Google Scholar
• Trambauer K, Adroguer B, and Fichot F, et al. Sarnet lecture notes on nuclear reactor severe accident phenomenology. IAEA, 2008; CEA-R--6194.
   Google Scholar
• Dinh TN, Nourgaliev RR. Turbulence modelling for large volumetrically heated liquid pools. Nucl Eng Des. 1997;169:131–150.
   Web of Science ®Google Scholar
• Shams A. Towards the accurate numerical prediction of thermal hydraulic phenomena in corium pools. Ann Nucl Energy. 2018;117:234–246.
   Web of Science ®Google Scholar
• Fukasawa M, Hayakawa S, Saito M. Thermal-hydraulic analysis for inversely stratified molten corium in lower vessel. J Nucl Sci Technol. 2008;45:873–888.
   Web of Science ®Google Scholar
• Zhang L, Zhang Y, Zhou Y, et al. COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers. Ann Nucl Energy. 2016;87:81–88.
   Web of Science ®Google Scholar
• Esmaili H, Khatib-Rahbar M. Analysis of in-vessel retention and ex-vessel fuel coolant interaction for AP1000. NUREG/CR 6849 ERTNRC O4 2OI. 2004. p. 138.
   Google Scholar