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Evaluation on coupling of wall boiling and population balance models for vertical gas-liquid Subcooled boiling flow of first loop of nuclear power plant

Hu, Guang; Ma, Yue; Liu, Qianfeng


An accurate prediction of the interphase behaviors of the vertical gas-liquid subcooled boiling flow is meaningful for the first loop of a nuclear power plant (NPP). Therefore, the interphase behaviors including the bubble size distribution in the first loop of the NPP are analyzed, evaluated, and validated using various wall boiling models coupled with the population balance model (PBM) kernels in this paper. Firstly, nondimensional numbers of the first loop of the NPP and DEBORA (Development of Borehole Seals for High-Level Radioactive Waste) experiment test cases are analyzed with approximation. Secondly, five active nucleation site density models N$_{n}$ coupled with the PBM kernel combination, four kernel combinations (C1~C4) with the N$_{n}$ models are calculated and analyzed. Lastly, various behaviors including the bubble size distribution Sauter mean diameter (SMD) d$_{p}$, void fraction α, gas superficial velocity j$_{g}$, and liquid superficial velocity j$_{i}$ are compared and validated with the experimental data of the DEBORA-1 (P = 2.62 MPa). The results indicate that the two Nn models are suitable for the calculations of thefirst loop of the nuclear power plant. ... mehr

Verlagsausgabe §
DOI: 10.5445/IR/1000140901
Veröffentlicht am 08.12.2021
DOI: 10.3390/en14217357
Zitationen: 3
Web of Science
Zitationen: 2
Zitationen: 3
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Thermische Energietechnik und Sicherheit (ITES)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2021
Sprache Englisch
Identifikator ISSN: 1996-1073
KITopen-ID: 1000140901
HGF-Programm 32.12.02 (POF IV, LK 01) Beyond Design Basis and Emergency Management
Erschienen in Energies
Verlag MDPI
Band 14
Heft 21
Seiten 7357
Nachgewiesen in Web of Science
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