Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel Bundles 期刊名称： Journal of Nuclear Science & Technology
作者： Yina ZHANG,Chao ZHANG,Jin JIANG
作者机构： Department of Mechanical and Materials Engineering,Department of Electrical and Computer Engineering
年份： 2011年
期号： 第6期
关键词： supercritical water-cooled nuclear reactor (scwr);heat transfer;fluid flow;cladding surface temperature (cst);numerical simulation
摘要：A supercritical water-cooled reactor (SCWR) was proposed as a kind of generation IV reactor in order to improve the efficiency of nuclear reactors. Although investigations on the thermal-hydraulic behavior in SCWR have attracted much attention, there is still a lack of CFD study on the heat transfer of
supercritical water in fuel channels. In order to understand the thermal-hydraulic behavior of supercritical fluids in nuclear reactors, the local fluid flow and heat transfer of supercritical water in a 37-element fuel bundle has been studied numerically in this work. Results show that secondary flow appears and the cladding surface temperature (CST) is very nonuniform in the fuel bundle. The maximum cladding surface temperature (MaxCST), which is an important design parameter for SCWR, can be predicted and analyzed using the
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