Numerical Investigation of the Effect of Grids and Turbulence Models on Critical Heat Flux in a Vertical Pipe

Numerical simulation has been widely used in nuclear reactor safety analyses to gain insight into key phenomena. The Critical Heat Flux (CHF) is one of the limiting criteria in the design and operation of nuclear reactors. It is a two-phase flow phenomenon, which rapidly decreases the heat transfer...

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Bibliographic Details
Main Authors: Xiaomeng Dong, Zhijian Zhang, Dong Liu, Zhaofei Tian, Guangliang Chen
Format: Article
Language:English
Published: Frontiers Media S.A. 2018-07-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/article/10.3389/fenrg.2018.00058/full