超临界水冷混合堆快谱区组件物理——热工分析  

A neutron-kinetics/thermal-hydraulics analysis of the fast zone assembly in the SCWR mixed core

作　　者：严勇[1] 刘晓晶[1] 程旭[1] 

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《核科学与工程》2009年第3期193-199,206,共8页Nuclear Science and Engineering

基　　金："973计划"项目(2007CB209800)

摘　　要：提出了超临界水冷混合堆快谱区多层燃料组件设计方案。应用MCNP程序为该组件建立计算模型,并进行了相应的物理计算;同时运用子通道分析程序STAFAS对多层燃料组件子通道进行了初步的稳态热工分析。计算结果表明:超临界水冷混合堆快谱区多层燃料组件燃料转换比超过1.0,并且获得负的冷却剂空泡反应性系数;燃料包壳表面最高温度约为595℃,低于设计准则规定的上限值,同时组件各子通道出口冷却剂温度均匀性较好。通过对燃料棒径敏感性分析可知,较大棒径组件燃料转换比较大,但也会导致热通道包壳表面温度峰值升高。This paper proposes a multi-layer design of fuel assemblies for the fast zone of the SCWR mixed core. Both neutron-physical and thermal-hydraulic behavior of the multi-layer fuel assembly are analyzed using the MCNP code and the sub-channel analysis code STAFAS, respectively. The results show that with the proposed multi-layer structure the fast zone of the mixed core has breeding capability. At the same time, a negative void reactivity coefficient of coolant can be achieved. The peak temperature of fuel cladding is about 595 ℃, which is lower than the design limit. In addition, a well uniform distribution of the coolant temperature at the exit of the fuel assembly is obtained with the reference geometric parameters. A sensitivity analysis indicates that a larger fuel rod diameter leads to a higher conversion ratio, however,results in a higher peak temperature of fuel claddings.

关 键 词：超临界水冷堆 混合堆芯 燃料组件 子通道分析 

分 类 号：TL33[核科学技术—核技术及应用]