钠冷快堆六角形组件换热特性分析  

Analysis of Heat Transfer Characteristic of Hexagonal Assemblyin Sodium-cooled Fast Reactor

作　　者：师泰 张东辉[1] 刘一哲[1] SHI Tai;ZHANG Donghui;LIU Yizhe(China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《原子能科学技术》2021年第2期211-218,共8页Atomic Energy Science and Technology

摘　　要：钠冷快堆乏燃料组件在转运过程中,会暴露在传热性能较差的氩气环境中。为保证燃料组件温度在转运过程中低于安全限值,本研究基于37棒燃料组件开展了在氩气环境下的实验研究及数值模拟计算。研究结果表明:可采用等效导热法对组件内绕丝模型进行简化,简化模型能满足计算精度要求。将计算结果与实验研究结果进行对比分析,结果表明数值模拟方法能较好模拟组件在氩气环境下的换热。六角形燃料组件在氩气中的换热分析中,辐射换热具有重要的影响,实验工况下辐射换热占总换热量的36%~57%。Spent fuel assemblies of the sodium-cooled fast reactors are exposed to an argon atmosphere with poor heat transfer performance during the transfer process.In order to ensure that the temperature of the fuel assembly is lower than the safety limit value during the transfer process,the experimental research and numerical simulation calculation were carried out under the argon atmosphere based on the 37 rods bundle fuel assembly in the paper.The research results show that the equivalent heat conduction method can be used to simply the wire-wrapped assembly,which can meet the calculation accuracy requirements.The calculation results were compared with the experimental research results,which proves that the numerical simulation method can simulate the fuel assembly heat transfer well.In the heat transfer analysis of hexagonal fuel assembly in argon atmosphere,the radiative heat transfer has an important influence.Under the experimental conditions,the radiative heat transfer accounts for 36%to 57%of the total heat transfer.

关 键 词：钠冷快堆 六角形组件 数值模拟 乏燃料 

分 类 号：TL33[核科学技术—核技术及应用]