Prediction of Critical Heat Flux for Subcooled Flow Boiling in Annulus and Transient Surface Temperature Change at CHF

نویسندگان

چکیده

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 subcooled flow boiling in rod bundles still remains unsolved. In this paper, we try the an annulus, which most basic geometry simplified fuel bundle, using liquid sublayer dryout model. validated with both water and R113 data, showing accuracy within ±30%. After annulus calculated successfully, near-wall vapor–liquid structure proposed on basis Modeling transfer modes over heating surface at performed, predictions changes thickness heater temperature occurrence point are carried out by solving conduction equation cylindrical coordinates convective boundary condition, change pattern surface. Transient reported.

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ژورنال

عنوان ژورنال: Fluids

سال: 2022

ISSN: ['2311-5521']

DOI: https://doi.org/10.3390/fluids7070230