压水堆冷却剂中硼酸浓度对核主泵性能影响研究  

Effect of Boric Acid Concentration on Reactor Coolant Pump Performance in PWRs

作　　者：张野[1] 王晓放[1] 介红恩[1] 

机构地区：[1]大连理工大学能源与动力学院,辽宁大连116024

出　　处：《核动力工程》2011年第4期95-98,117,共5页Nuclear Power Engineering

基　　金：973国家重点基础研究资助项目(2009CB724303)

摘　　要：采用Fluent软件对混流式核主泵叶轮在多流量工况和冷却剂中含有不同浓度硼酸溶液的多方案进行三维湍流流动数值模拟,结合实验数据,分析了清水与硼酸溶液对核主泵性能影响的差异,着重研究了硼酸浓度对叶轮的影响程度,并对采用数值计算方法预测核主泵中以清水作为模拟介质的可行性进行了分析。结果表明,即使在极限硼酸浓度下,冷却介质中硼酸浓度亦对核主泵性能影响较小。由此验证了采用清水作为模拟介质是可行的。Using the computational fluid dynamics software Fluent,the three-dimensional turbulent flow of the reactor coolant pump（RCP） impeller at different flow rates and different concentrations of boric acid is simulated.With the experimental data,different effects on RCP performance are analyzed between water and boric acid,especially the influence to the impeller.The feasibility of taking the water as coolant in RCP by using numerical simulation method is analyzed,and the result shows that negligible differences in water and boric acid was acquired even in abnormal concentration of boric acid.It proved that the using of water as coolant when conducting a simulation is feasible.

关 键 词：硼酸 核主泵 性能影响 数值模拟 

分 类 号：TL343[核科学技术—核技术及应用] TH313[机械工程—机械制造及自动化]