Published February 2013 | Version v1
Journal article

Experimental study on heat transfer of supercritical water in simple channels

  • 1. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu (China)

Description

Heat transfer experiments of supercritical water in circular tube, circular annulus and rectangular annulus were carried out, which were abstracted as simple channels to represent the thermal hydraulic characteristics of several Supercritical Water Cooled Reactor (SCWR) fuel assembly design. It was found that, the effect of heat flux, mass flux and pressure on supercritical water heat transfer performance in different simple channels was similar in general. Under the same mass flux and pressure, there was a peak of heat transfer coefficient in pseudo-critical area, which would be decreased with the increasing of heat flux. Under the same heat flux and pressure, the heat transfer coefficient at the same bulk fluid enthalpy would be increased with the increasing of mass flux. The effect of pressure on supercritical water heat transfer performance in different simple channels was not strong except in the pseudo-critical area where the peak of heat transfer coefficient would occur. The heat transfer deterioration phenomenon was also found at different pressures and mass fluxes in different simple channels. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
34
Journal Issue
1
Journal Page Range
p. 101-107
ISSN
0258-0926

Optional Information

Notes
17 figs., 1 tab., 4 refs.