Numerical Simulation and Safety analysis on Flow Field of a 1000 MW Unit Nuclear reactor pressure vessel

被引:0
|
作者
Liu Jian-quan [1 ]
Sun Bao-min [1 ]
Hu Yong-sheng [1 ]
Bai Tao [1 ]
机构
[1] N China Elect Power Univ, Key Lab Condit Monitoring & Control Power Plant E, Beijing, Peoples R China
关键词
circuit fault; circuit isolation layer; flow field; numerical simulation; realizable k-epsilon model;
D O I
暂无
中图分类号
TP [自动化技术、计算机技术];
学科分类号
0812 ;
摘要
The flow field of a 1000 MW unit nuclear reactor pressure vessel operation process was numerically studied with realizable k-epsilon model. the reactor normal operating, circuit fault and isolation layer being plug conditions were studied. The different reactor flow characteristics between normal operating and two fault conditions were compared. The numerical simulation results show as follows, The core inlet flow distribution is certain heterogeneity during normal operation, flow velocity are fast in the core inlet middle and surrounding area, The core inlet annular channel blocking zone has a certain regulation to the flow distribution, Increasing flow resistance coefficient, Core inlet flow is more evenly; in circuit fault condition, Other loop currents can add flow to the loop; reduce flow resistance coefficient, Core inlet flow is more evenly, too large resistance coefficient can enlarge heterogeneity flow distribution, The numerical simulation results provide a theoretical basis to judge flow field when circuit fault and isolation layer being plug conditions, it can also provide some theoretical basis for the nuclear reactor pressure vessel operation.
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收藏
页数:4
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