Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant

An accurate prediction of the interphase behaviors vertical gas-liquid subcooled boiling flow is meaningful for first loop a nuclear power plant (NPP). Therefore, including bubble size distribution in NPP are analyzed, evaluated, and validated using various wall models coupled with population balance model (PBM) kernels this paper. Firstly, nondimensional numbers DEBORA (Development Borehole Seals High-Level Radioactive Waste) experiment test cases analyzed approximation. Secondly, five active nucleation site density Nn PBM kernel combination, four combinations (C1~C4) calculated analyzed. Lastly, Sauter mean diameter (SMD) dp, void fraction α, gas superficial velocity jg, liquid jl compared experimental data DEBORA-1 (P = 2.62 MPa). The results indicate that two suitable calculations thefirst plant. For instance, SMD specified C1 (maximum relative error 9.63%) has relatively better NPP. Especially, combination applicable calculation α while C4 jg. These can provide guidance numerical computation