CFD-Assisted model development for estimation of hole-ablation diameter of a pressure vessel during severe accidents

作者: Moon Won Song , Hee Cheon NO

DOI: 10.1016/J.NUCENGDES.2019.110191

关键词: Superficial velocityHeat transfer coefficientCoriumPressure vesselTurbulenceSuperheatingFlow (psychology)Reactor pressure vesselMechanicsMaterials science

摘要: Abstract To evaluate the released radioactive materials to an environment under a nuclear severe accident, it is necessary analyze ex-vessel phenomena. The releasing diameter one of most essential parameters estimate enlarged because wall reactor vessel melts due high temperature corium flow. In this study, hole-ablation model was developed based on one-dimensional heat balance equations for molten flow, crust layer, and layer vessel, respectively. Moreover, transfer coefficient situation discharging flow obtained using computational-fluid-dynamics. As result, we proposed enhancement factor, 1.57, be multiplied by external turbulent We found out that strong effect critical thickness thicknesses layer. suggested relationship between ratio superficial velocity compared with Pilch model: mean averaged error (MAE) present 9.51%, whereas 36.13%. case low superheat where can produced, without formation predicts much larger final-hole than does.

参考文章(18)
Michael Epstein, Michael A. Grolmes, Robert E. Henry, Hans K. Fauske, Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel Nuclear Science and Engineering. ,vol. 61, pp. 310- 323 ,(1976) , 10.13182/NSE76-A26917
D Magallon, H Hohmann, Experimental investigation of 150-kg-scale corium melt jet quenching in water Nuclear Engineering and Design. ,vol. 177, pp. 321- 337 ,(1997) , 10.1016/S0029-5493(97)00201-X
A. Yim, M. Epstien, S.G. Bankoff, G.A. Lambert, G.M. Hauser, Freezing-melting heat transfer in a tube flow International Journal of Heat and Mass Transfer. ,vol. 21, pp. 1185- 1196 ,(1978) , 10.1016/0017-9310(78)90137-0
C.C. Chu, J.J. Sienicki, B.W. Spencer, W. Frid, G. Löwenhielm, Ex-vessel melt-coolant interactions in deep water pool: studies and accident management for Swedish BWRs Nuclear Engineering and Design. ,vol. 155, pp. 159- 213 ,(1995) , 10.1016/0029-5493(94)00874-X
T.N. Dinh, V.A. Bui, R.R. Nourgaliev, T. Okkonen, B.R. Sehgal, Modelling of heat and mass transfer processes during core melt discharge from a reactor pressure vessel Nuclear Engineering and Design. ,vol. 163, pp. 191- 206 ,(1996) , 10.1016/0029-5493(95)01167-6
A. Annunziato, A. Yerkess, C. Addabbo, FARO and KROTOS code simulation and analysis at JRC Ispra Nuclear Engineering and Design. ,vol. 189, pp. 359- 378 ,(1999) , 10.1016/S0029-5493(98)00268-4
Vladimir Melikhov, Oleg Melikhov, Sergey Yakush, Nikita Rtishchev, Validation of Fuel-Coolant Interaction Model for Severe Accident Simulations Science and Technology of Nuclear Installations. ,vol. 2011, pp. 1- 11 ,(2011) , 10.1155/2011/560157
G. Berthoud, M. Valette, Development of a multidimensional model for the premixing phase of a fuel-coolant interaction Nuclear Engineering and Design. ,vol. 149, pp. 409- 418 ,(1994) , 10.1016/0029-5493(94)90306-9
M. Epstein, H.K. Fauske, Applications of the Turbulent Entrainment Assumption to Immiscible Gas-Liquid and Liquid-Liquid Systems Chemical Engineering Research & Design. ,vol. 79, pp. 453- 462 ,(2001) , 10.1205/026387601750282382