EXPERIMENTAL RESEARCH ON HEAT TRANSFER OF SUPERCRITICAL WATER UPFLOWING IN VERTICAL TUBE
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:
Yongliang Li (Nuclear Power Institute of China)
Zhigang Huang (Nuclear Power Institute of China)
Xiaokang Zeng (Nuclear Power Institute of China)
Xiao Yan (Nuclear Power Institute of China)
Yanping Huang (Nuclear Power Institute of China)
Zejun Xiao (Nuclear Power Institute of China)
  

Abstract

Heat transfer experiments in vertical tube were performed in Supercritical Water Thermal-hydraulic Mechanism Test (SCTM) Loop in Nuclear Power Institute of China. The test tube was 3.0 m long and the inner diameter of 6.0 mm. Experimental condition covered pressures of 23, 24 and 25MPa, mass flux of 600-1200 kg/m2•s, heat flux of 600-1100kW/m2, and bulk temperatures of 300-500℃.  The experimental data were compared with several current correlations, respectively. It showed that these correlations could not predict heat transfer coefficient accurately in pseudo-critical area.

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