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