基于CFD的池式快堆多物理耦合分析方法研究  

Research on Multi-Physics Coupling Method of Pool Type Fast Reactor Based on CFD

作　　者：赵鹏程[1,2,3] 刘紫静 于涛[1] 刘佩琪[1] 谢金森 陈珍平[1] Zhao Pengcheng;Liu Zijing;Yu Tao;Liu Peiqi;Xie Jinsen;Chen Zhenping(School of Nuclear Science and Technology,University of South China,Hengyang,Hunan,421001,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment,University of South China,Hengyang,Hunan,421001,China)

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001 [2]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213 [3]南华大学核燃料循环技术与装备湖南省协同创新中心,湖南衡阳421001

出　　处：《核动力工程》2020年第6期36-44,共9页Nuclear Power Engineering

基　　金：核反应堆系统设计技术国家级重点实验室重点基金项目(6142A07180110);国防科技工业核动力技术创新中心科研项目(HDLCXZX-2017-HD-017);国家自然科学基金青年项目(11905101);湖南省自然科学基金(2019JJ40239,2020JJ5465);核反应堆系统设计技术重点实验室运行基金资目(HT-KFKT-10-2018001);湖南省教育厅优秀青年项目(18B270,19B494);南华大学核燃料循环技术与装备湖南省协同创新中心开放基金重点项目(2019KFZ08)。

摘　　要：基于临界/次临界点堆中子动力学模型、燃料棒传热模型、热交换器和多孔介质等辅助热工水力模型,采用显式迭代和动态链接库技术(DLL),利用商用计算流体力学(CFD)程序FLUENT的用户自定义函数(UDF)实现中子动力学、燃料棒热传导等和快堆堆池冷却剂流动换热的耦合计算,开发池式快堆多物理耦合计算程序CFD/PF。采用CFD/PF开展小型自然循环铅铋快堆SNCLFR-10无保护超功率事故(UTOP)模拟,并与国际知名快堆多物理耦合分析程序SIMMR-Ⅲ的计算结果开展Code-to-Code对比分析。研究结果表明:CFD/PF与SIMMER-Ⅲ的分析结果吻合良好,耦合程序的开发取得了初步成功,可用于分析池式快堆堆池内的复杂三维流动和换热现象。Based on the critical/subcritical point kinetics model,the fuel pin heat transfer model,and the auxiliary thermal hydraulic models such as the heat exchanger model and the porous media model,a multi-physical coupling code CFD/PF was developed by means of the explicit iteration method,dynamic link library technique(DLL)and user-defined functions(UDF)of FLUENT.The CFD/PF was used to carry out the simulation of SNCLFR-100 unprotected transient of over power(UTOP)of a small natural circulation LBE cooled fast reactor,and the code-to-code comparison analysis was conducted with the renowned multi-physical coupling code SIMMER-Ⅲ.The results indicated that the CFD/PF simulation results are in a good agreement with SIMMER-Ⅲcalculation results,and the multi-physical analysis method and code development have been achieved initial success,which can be used to analyze the complex three-dimensional flow and heat transfer phenomena in pool-type fast reactors.

关 键 词：池式快堆 多物理耦合 计算流体力学(CFD) 点堆动力学模型 燃料棒传热模型 

分 类 号：TL364[核科学技术—核技术及应用]