Prediction of Critical Heat Flux for Subcooled Flow Boiling in Annulus and Transient Surface Temperature Change at CHF
The ability to predict critical heat flux (CHF) is of considerable interest for high-heat equipment, including nuclear reactors. CHF prediction from a mechanistic model for subcooled flow boiling in rod bundles still remains unsolved. In this paper, we try to predict the CHF in an annulus, which is...
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| Format: | Article |
| Language: | English |
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MDPI AG
2022-07-01
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| Series: | Fluids |
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| Online Access: | https://www.mdpi.com/2311-5521/7/7/230 |