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) ;
  • Chang, Soon-Heung (Department of Nuclear Engineering Korea Advanced Institute of Science and Technology)
  • 발행 : 1997.05.01

초록

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/$m^2$ and the inlet subcooling of 350 and 450 kJ/kg, for stable upward flow with water as a coolant. Flow regime analysis has been performed for obtained CHF data with Mishima's flow regime map, which reveals that most of the CHF occur in the annular-mist flow regime. General parametric trends of the collected CHF data are consistent with those of previous studies. However, for the pressure effect on CHF, two different are observed; For relatively high mass flux, CHF increases with pressure and far lower mass flux, CHF decrease with pressure. Using modern data regression tool, ACE algorithm, two new CHF correlations for LPLF condition are developed based on local condition and inlet condition, respectively. The developed CHF correlations show better prediction accuracy compared with existing CHF prediction methods.

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