Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.10a
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- Pages.546-551
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- 1997
A Dry-Spot Model for the Prediction of Critical Heat Flux in Water Boiling in Bubbly Flow Regime
- Ha, Sang-Jun (Korea Advanced Institute of Science and Technology) ;
- No, Hee-Cheon (Korea Advanced Institute of Science and Technology)
- Published : 1997.10.01
Abstract
This paper presents a prediction of critical heat flux (CHF) in bubbly flow regime using dry-spot model proposed recently by authors for pool and flow boiling CHF and existing correlations for forced convective heat transfer coefficient, active site density and bubble departure diameter in nucleate boiling region. Without any empirical constants always present in earlier models, comparisons of the model predictions with experimental data for upward flow of water in vertical, uniformly-heated round tubes are performed and show a good agreement. The parametric trends of CHF have been explored with respect to variations in pressure, tube diameter and length, mass flux and inlet subcooling.
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