Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.05a
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- Pages.356-361
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- 1997
Experimental Study and Correlation Development of Critical Heat Flux under Low Pressure and Low Flow Condition
- Kim, Hong-Chae (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) ;
- Kim, Han-Kon (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 : 1997.05.01
Abstract
To investigate parametric effect on CHF and to get CHF data, experimental study has been performed with vertical round tubes under the condition of low pressure and low flow (LPLF). Test sections are made of Inconel-625 tube and have the geometry of 8 and 10 mm in diameter, and 0.5 and 1.0 m in heated length. All experiments have been conducted at the pressure of under 9 bar, the mass flux of under 250 kg/
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