AN EXPERIMENTAL STUDY OF CRITICAL HEAT FLUX IN A TUBE FOR NEAR-CRITICAL PRESSURES
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
Heat-Transfer Experiment (II)

Authors:
Yuzhou Chen (China Institute of Atomic Energy)
Chunsheng Yang (China Institute of Atomic Energy)
Minfu Zhao (China Institute of Atomic Energy)
Keming Bi (China Institute of Atomic Energy)
Kaiwen Du (China Institute of Atomic Energy)
Shuming Zhang (China Institute of Atomic Energy)
  

Abstract

The experiment of critical heat flux was conducted in a tube of inner diameter of 7.95 mm and heating length of 0.8 m with water flowing upward, covering the ranges of pressure of 8.6 – 20.9 MPa, mass flux of 447 – 1179 kg/m2s, outlet subcooling of 1 – 96 K and critical heat flux of 0.69 – 3.68 MW/m2. The CHF characteristics and parametric trends are studied, and the experimental results are compared with the predictions of 96 CHF Look-up Table.

 

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