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WANG SHAOPING;JIANG LI;SHEN MENGYU(Department of Engineering Mechanics,Tsinghua University)  
The research of thermal-hydraulic analysis of nuclear reactor core has been developed rapid-ly during recent years.In this paper, an efficient thermal-hydraulic analysis method of nuclearreactor core is presented. According to the characteristic of reactor core, some basic assumption isintroduced. Based on the subchannel analysis theory, mathematical model and governing equa-tions are set up to describe fluid flow and heat transfer in the core. In order to describe two phaseflow character,Slipping Model is included and the effect of subcooled boiling is also considered. Some constitutive relations are provided to define void fraction, turbulent mixing, drag coefficientand other thermal dynamic parameters. As for the solution of the equations,the finite differencemethod is used to discretise the governing equations. The discretised equation of pressure is ac-quired from momentum and continuity equations,different from the widely used COBRA code. At the end of this paper,the numerical results of rectangular and circular rod bundles are given tocompare with experimental data, showing the feasibility and reliability of this recently developedcomputer code.
【Fund】: 国家博士后科学基金
【CateGory Index】: TL33
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Chinese Journal Full-text Database 10 Hits
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