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 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 v...

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Bibliographic Details
Main Authors: Guang Hu, Yue Ma, Qianfeng Liu
Format: Article
Language:English
Published: MDPI AG 2021-11-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/14/21/7357