秦山核电站二期反应堆堆芯流量分配数值分析  

Numerical analysis of flow distribution at the reator core inlet of Qinshan phase-Ⅱ reactor

作　　者：张曙明[1] 李华奇[2] 赵民富[1] 陈玉宙[1] 杨夷[1] 卫光仁[1] 

机构地区：[1]中国原子能科学研究院,北京102413 [2]中国核动力研究设计院,四川成都610041

出　　处：《核科学与工程》2010年第4期299-307,共9页Nuclear Science and Engineering

基　　金：空泡物理和自然循环重点实验室基金资助项目(9140C7109030604)

摘　　要：获得可靠的堆芯入口流量分配数据是改善压水堆堆芯热工水力性能的需要。应用计算流体力学方法研究了反应堆压力壳内复杂的流动现象,得到了秦山核电站二期600 MW反应堆1/4整体水力模型的堆芯入口流量分配状况,并对下腔室几何结构、冷管段入口流量等影响因素进行了敏感性研究。分析结果表明,双环路工况入口流量对堆芯入口流量分配影响较小;与双环路工况相比,单环路运行工况时流动特性显著变化,导致流量分配状况差异较大;堆芯入口流量再分配因子为0.05,与原型设计参数吻合。计算结果证实所采用研究方法有效,可为相关反应堆工程设计验证提供依据。To improve the thermal hydraulic performance of pressurized water reactor（PWR）,it is of great importance to obtain reliable flow distribution data at the core inlet.Through computational fluid dynamics（CFD） analysis the flow field in a 1/4 scale model of the 600 MW PWR was worked out numerically.The sensitivity analysis focused on factors such as the lower plenum geometry and 500,880,900 m3/h of flow rate for an inlet nozzle,respectively.The results provided a deep understanding of the flow behavior concerning the pressure vessel of the PWR.Numerical results indicated that flow distribution at the core inlet is not sensitive to the inlet nozzle flow rate under two-loop operation mode.Moreover,flow characteristics inside the pressure vessel under single loop operation mode differ significantly from those under two-loop operation mode.A dimensionless flow distribution subfactor of 0.05 is in good agreement with the prototype design.The validity of applying CFD methods in flow distribution for nuclear reactor is verified.The analysis results are useful for the thermal hydraulic design of the PWR.

关 键 词：反应堆堆芯 下腔室 流量分配 计算流体力学 

分 类 号：TL32[核科学技术—核技术及应用]