Experimental Research on Heat Transfer of Supercritical Water Upflowing in Vertical Tube

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.