Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1996.05b
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- Pages.349-355
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- 1996
Derivation of Mechanistic Critical Heat Flux Model and Correlation for Water Based on Flow Excursion
- Chang, Soon-Heung (Department of Nuclear Engineering Korea Advanced Institute of Science and Technology) ;
- 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)
- Published : 1996.05.01
Abstract
In this study, the mechanistic critical heat flux (CHF) model and correlation for water are derived based on flow excursion (or Ledinegg instability) criterion and the simplified two-phase homogeneous model. The relationship between CHF for the water and the principal parameters such as mass flux heat of vaporization, heated length-to-diameter ratio, vapor-liquid density ratio and inlet subcooling is derived on the developed correlation. The developed CHF correlation predicts very well at the applicable ranges, 1 < P < 40 bar, 1, 300 < G 27, 00 kg/
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