Prediction of critical heat flux in a rod bundle channel with spacer grids based on the Eulerian two-fluid model

The critical heat flux (CHF) is a vital parameter influencing the safety and efficiency of reactor cores. In this study, the Eulerian two-fluid model coupled with the extended wall boiling model in STAR-CCM+ was employed to simulate the departure from nucleate boiling (DNB) phenomenon in a 5 × 5 pre...

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Bibliographic Details
Main Authors: Li Kejia, Zheng Xiong, Meng Shuqi, Jin Desheng, Mao Yulong, Hu Yisong, Zhou Youxin, Chen Jun
Format: Article
Language:English
Published: Frontiers Media S.A. 2025-01-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2024.1366902/full