首页 | 本学科首页   官方微博 | 高级检索  
     

超临界水冷堆双排燃料组件子通道分析
引用本文:许志红,杨晓,傅晟威,杨燕华.超临界水冷堆双排燃料组件子通道分析[J].核科学与工程,2012,32(1):56-62.
作者姓名:许志红  杨晓  傅晟威  杨燕华
作者单位:1. 上海变通大学核科学与工程学院,上海,200240
2. 海军工程大学核能科学与工程系,湖北武汉,430000
基金项目:国家“973”计划资助项目,上海市自然科学基金资助项目
摘    要:研究基于Cobra-IV程序,开发了适用于超临界水冷堆燃料组件分析的子通道程序.针对超临界水冷堆慢谱双排组件,进行了稳态计算,获取了相关组件热工水力参数.在此基础上,针对单一通道进行了瞬态计算,分析了燃料棒线功率变化和冷却剂流量变化条件下,超临界水冷堆燃料组件的流动和传热的动态响应,为超临界水冷堆组件的优化设计提供了参考.

关 键 词:超临界水冷堆  双排燃料组件  子通道分析

Analysis of the sub-channel of SCWR two-row fuel assembly
XU Zhi-hong , YANG Xiao , FU Sheng-wei , YANG Yan-hua.Analysis of the sub-channel of SCWR two-row fuel assembly[J].Chinese Journal of Nuclear Science and Engineering,2012,32(1):56-62.
Authors:XU Zhi-hong  YANG Xiao  FU Sheng-wei  YANG Yan-hua
Affiliation:1(1.School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China; 2.Department of Nuclear Energy Science and Engineering,Navy University of Engineering,Wuhan of Hubei Prov.430000,China)
Abstract:Based on the COBRA-IV code,a new sub-channel code system developed for the supercritical water cooled reactor(SCWR) fuel assembly is analyzed.In order to optimize the SCWR fuel assembly design,a sub-channel analysis of two rows SCWR fuel assembly is performed,including steady-state and transient calculation.For the steady-state calculation,several channel’s parameters are selected to evaluate the thermal-hydraulic performance of the fuel assemblies.Based on the steady-state results,two transient calculations(change of fuel rod power and change of coolant flow) are carried out to estimate the dynamic behavior of the fuel assemblies.The results achieved so far indicate a good applicability of the sub-channel code for the SCWR fuel assembly analysis,which is good for the future optimization of SCWR fuel assembly design.
Keywords:supercritical water cooled reactor(SCWR)  two-row fuel assembly  sub-channel analysis
本文献已被 CNKI 万方数据 等数据库收录!
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号