Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1996.11a
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- Pages.242-247
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- 1996
Development of Critical Heat Flux Correction Factor for Water under Flow Oscillation Conditions
- Kim, Yun-Il (Department of Nuclear Engineering Korea Advanced Institute of Science and Technology) ;
- Baek, Won-Pil (Department of Nuclear Engineering Korea Advanced Institute of Science and Technology) ;
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Chang, Soon-Heung
(Department of Nuclear Engineering Korea Advanced Institute of Science and Technology)
- Published : 1996.11.01
Abstract
Flow oscillations in boiling channels induces a drastic reduction of the (critical heat flux) CHF or premature burnout. However, most of CHF works and correlations have been focused on stable flow conditions without considering flow oscillation. Therefore to improve the understanding on flow oscillation CHF, in this paper a new CHF correction factor to predict the CHF values under flow oscillation conditions has been developed from 126 experimental data. Also to investigate the dominant factor on flow oscillation CHF parametric trends are analyzed by using the developed correction factor. The overall mean accuracy ratio of the developed correction factor is 1.033 with a standard deviation of 0.195. The RMS errors 0.198. Its assessment shows that the predictions agree well with the experimental data within 25% error bounds.
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