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《CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING》 1995-04
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ANEFFICIENT THERMAL-HYDRAULIC ANALYSIS METHOD OF NUCLEAR REACTOR CORE

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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【Co-citations】
Chinese Journal Full-text Database 10 Hits
1 Xiao Zejun, Chen Binde, Zhao Hua, Jiang Xulun Xiao Zejun (Chengdu, Nuclear Power Research and Design Institute), Chen Binde, Zhao Hua, Jiang Xulun.;Experimental Research on the Frictional Resistance of low Velocity Steam Fluid Two Phese Mass Flows in Vertical Riser Pipes[J];POWER EQUIPMENT;1998-06
2 Yan Changqi(Harbin Shipbuilding Engineering Institute);The Calculation of Two-Phase Flow Pressure Drop in Reactor Fuel Elements'Spacer Grid[J];Nuclear Power Engineering;1990-01
3 Bo Jinhai;Jiang Shengyao;Yao Meisheng;Tong Yunxian;Zhang Youjie;Wu Shaorong(Institute of Nuclear Energy Technology,Tsinghua University,Beijing);Simulation Experiment of Small Break LOCA in Upper Plenum[J];Nuclear Power Engineering;1990-05
4 SONG Xiao-ming,ZHANG Li-wu,WANG Jian-min,LIU Ding-ming,LU Jian-chao (Nuclear Power Instiutte of China,Chengdu 610041,China);Development of Steady-State Thermal Hydraulic Analysis Code for Rectangle Channel Core[J];Nuclear Power Engineering;2002-03
5 XIAO Ze-jun 1,CHEN Bing-de2,LI Zhong-peng2,JIA Dou-nan1 (1. Xi’an Jiaotong University,Xi’an,710049,China;2. Nuclear Power Institute of China,Chengdu,610041,China);Research Progress of Experiment on Critical Heat Flux[J];Nuclear Power Engineering;2003-01
6 LIAO Yi-xiang1,ZHANG Wen-xing1,JIA Dou-nan2,YU Tao1 (1. Nanhua University,Hunan,421001,China;2. Xian Jiaotong University,710049,China);The Development of a Safety Analysis Code——SAC-PREARS[J];Nuclear Power Engineering;2003-04
7 DONG Yong-sheng, ZHANG Jian-min ( Xi'an Jiaotong University. 710049, China);Modeling and Steady-state Analysis for a Horizontal Steam Generator[J];Nuclear Power Engineering;2004-03
8 LU Qing1,2,QIU Sui-zheng1,2,TIAN Wen-xi1,2,SU Guang-hui1,2(1.State Key Laboratory of Multi Phase Flow in Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China;2.Department of Nuclear Engineering,Xi’an Jiaotong University,Xi’an,710049,China);Investigation on Mass Flux Distribution and Asymmetrical Cooling in A Plate-Type Fuel Reactor[J];Nuclear Power Engineering;2008-02
9 XU Jian-jun,CHEN Bing-de,XIONG Wan-yu,WANG Xiao-jun,WANG Fei(National Key Laboratory of Bubble Physics & Natural Circulation,Nuclear Power Institute of China,Chengdu,610041,China);Numerical Simulation of Hydrodynamic Mixing in Narrow Rectangular Multi-Channel[J];Nuclear Power Engineering;2008-03
10 TIAN Wen-xi1,QIU Sui-zheng1,SU Guang-hui1,JIA Dou-nan1,ZHANG Jian-wei2 (1.State Key Iaboratory of Multi-phase Flow in Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China; 2.Department of Reactor Engineering Research and Design,China Institute of Atomic Energy,Beijing,102413,China);Accident Analysis of Station Blackout for China Advanced Research Reactor with Shutdown Failure[J];Nuclear Power Engineering;2008-03
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