Research On Heat Transfer Characteristics Of Supercritical Water In The Vertical Tube

As the only type of water-cooled reactor among the six advanced nuclear energysystems recommended by the Gen-IVInternational Forum, Supercritical Water-CooledReactor(SCWR)has the prominent advantages of high thermal efficiency, systemsimplicity, small size and competitive economics. Among the fundamental researchesrelated to the SCWR design, the investigation on the heat transfer characteristics andmechanism of fluids at supercritical pressures has received great attention.Based on the requirement of SCWR research and engineering design, theexperiment on the heat transfer performance of supercritical water in vertical tubes ofdiameter7.6mm and10mm has been carried out on the supercritical watermultiple-purpose test loop in Shanghai Jiao Tong University. Experimental data areobtained in a large range of parameters. Through the analysis of the data, themechanism of forced convective heat transfer in tubes of supercritical fluids and theeffects of various factors on supercritical heat transfer are investigated. Thecorrelations proposed by previous researches have been extensively collected. Bycomparing the predictions of these correlations with the experimental data, error andaccuracy analysis for the correlations is presented. The relativity between thedimensionless numbers representing the buoyancy and thermal acceleration and theexperiment data is obtained. Finally, the heat transfer of supercritical water isnumerically simulated using k-ωSST turbulence model and the mechanism of the heattransfer deterioration phenomenon in vertical tubes is uncovered.The experiment data of supercritical water heat transfer obtained and theanalyzing work in this article have established a solid foundation for further researchof proposing new supercritical heat transfer correlation and the analysis for the heattransfer characteristics of supercritical fluid in rod bundles.