欠热条件下非能动余热排出热交换器传热试验数值模拟  

Numerical Simulation on Heat Transfer Experiment of Passive Residual Heat Removal Heat Exchanger at Subcooled Condition

作　　者：李伟卿[1] 赵民富[1] 段明慧[1] 陈玉宙[1] 王含 

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413 [2]国核华清(北京)核电技术研发中心有限公司,北京102209

出　　处：《原子能科学技术》2016年第8期1410-1415,共6页Atomic Energy Science and Technology

基　　金：国家科技重大专项资助项目(2011ZX06004-007-001)

摘　　要：针对大型先进压水堆非能动余热排出热交换器设计和安全分析计算模型存在的重要缺陷,以AP1000的非能动余热排出热交换器为原型,采用3根C型管进行了非能动余热排出热交换器传热试验。然后采用流体计算软件对欠热试验工况进行了数值模拟,通过多次计算得到了传热管外传热计算可采用的传热关系式,选取的传热模型下的计算结果与试验结果符合较好。利用传热模型验证了AP1000的设计工况,发现AP1000非能动余热排出热交换器的设计能带走堆芯余热。本文研究可为大型先进压水堆设计和安全分析提供技术支撑。In this study,the passive residual heat removal heat exchanger of AP1000 was used as the prototype.A heat transfer experiment of passive residual heat removal heat exchanger with three C-type tubes was carried out.And then subcooled test conditions were numerically simulated by CFD software.Through numerical calculation,the correlations for calculating the heat transfer of the outside of the tube were obtained.The calculated results using the adopted heat transfer model were in good agreement with the experimental data.With the heat transfer model,the design condition of AP1000 was also verified.It shows that the heat exchanger of AP1000 can remove the core residual heat.Therefore,the model is properly conservative and it can provide a techni-cal support for design and safety analysis of large advanced pressurized water reactor.

关 键 词：非能动余热排出热交换器 传热模型 AP1000 

分 类 号：TL32[核科学技术—核技术及应用]