| 反应堆热工物理耦合反馈变量敏感性分析 |
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| 引用本文： | 王琮,曹欣荣.反应堆热工物理耦合反馈变量敏感性分析[J].原子能科学技术,2013,47(Z1):283-286. |
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| 作者姓名： | 王琮 曹欣荣 |
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| 作者单位： | 1.武汉第二船舶设计研究所，湖北 武汉430000；2.哈尔滨工程大学 核科学与技术学院，黑龙江 哈尔滨150001 |
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| 摘 要： | 在反应堆设计计算中，堆芯热工水力和堆芯物理的耦合十分重要。本文以秦山二期核电站反应堆堆芯作为研究对象，使用栅元计算程序CASMO4E对各类型的组件进行均匀化参数的计算；完成热工物理耦合反馈变量的敏感性分析；采用两种方法生成耦合需要的截面库，并对其进行误差分析。
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| 关 键 词： | 热工物理耦合 CASMO4E 敏感性分析 误差分析 |
Sensitivity Study of Feedback Parameters for Thermal-Hydraulic Coupling Code |
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| WANG Cong,CAN Xin-rong.Sensitivity Study of Feedback Parameters for Thermal-Hydraulic Coupling Code[J].Atomic Energy Science and Technology,2013,47(Z1):283-286. |
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| Authors: | WANG Cong CAN Xin-rong |
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| Affiliation: | 1.Wuhan 2nd Ship Design and Research Institute, Wuhan 430000, China;2.College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150001, China |
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| Abstract: | Thermal-hydraulic coupling code is important for reactor core design. In this paper, the reactor core of Qinshan-Ⅱ nuclear power plant was selected as study object. CASMO4E was used to calculate the assembly homogenized parameters. The sensitivity study of independent parameters used in thermal-hydraulic coupling code was finished. Two kinds of cross-section tables were established, and the error analysis of these two cross section tables was finished. |
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| Keywords: | thermal-hydraulic coupling CASMO4E sensitivity study error analysis |
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