超临界水冷堆堆芯简化模型流量分配研究  

Code Research on Mass Flux Assignment of Spuercritical Water-Cooled Reactor

作　　者：李臻洋[1] 周涛[1] 孙灿辉[1] 

机构地区：[1]华北电力大学核热工安全与标准化研究所,北京102206

出　　处：《核动力工程》2011年第3期52-57,共6页Nuclear Power Engineering

基　　金：国家重点基础研究发展计划(973计划)(2007CB209800)

摘　　要：选取超临界水冷堆(SCWR)燃料组件作为研究对象,在平均孔口尺寸条件下,对堆芯功率分布进行模拟,建立了热工水力计算模型并进行了程序的开发,计算出了各个并联通道内的冷却剂流量以及相关参数分布。结果表明,平均孔口尺寸条件得到的各组群燃料通道轴向密度分布、堆芯功率分布存在较大的不均匀性,致使流量分配存在较大的差异;通过增大高功率组群的孔板尺寸即可得到较为合理的热工水力参数分布。Taking the fuel assembly of thermal spectrum supercritical water-cooled reactor（SCWR） as the research object,and on the condition of average orifice size,the reactor core power distribution is simu-lated,and the thermal hydraulic calculation model is established and the corresponding program is developed.The coolant mass flux distribution and related parameters distributions in the parallel channels is calculated.The results show that the axial density distribution and distribution core power of each fuel assembly group channels is very inhomogeneous,causing a large mass flux difference,which could be resolved through in-creasing the orifice size of high power fuel assembly groups.

关 键 词：超临界水冷堆 流量分配 热工水力 

分 类 号：TK112[动力工程及工程热物理—热能工程]