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

作　　者：许志红[1] 杨晓[1] 傅晟威[2] 杨燕华[1] 

机构地区：[1]上海交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

出　　处：《核科学与工程》2012年第1期56-62,共7页Nuclear Science and Engineering

基　　金：国家"973"计划资助项目(2007CB209800);上海市自然科学基金资助项目(11ZR1416900)

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。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.

关 键 词：超临界水冷堆 双排燃料组件 子通道分析 

分 类 号：TK122[动力工程及工程热物理—工程热物理]