环形燃料混合堆芯横向流动特性数值模拟研究  

Numerical Simulation of Cross Flow Characteristic for Annular Fuel Mixed Core

作　　者：胡立强[1] 田子豪 季松涛[1] 何晓军[1] HU Liqiang;TIAN Zihao;JI Songtao;HE Xiaojun(Reactor Engineering Technology Research Institute,China Institute of Atomic Energy,Beijing 102413,China;School of Mechanical,Electronic and Control Engineering,Beijing Jiaotong University,Beijing 100044,China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究所,北京102413 [2]北京交通大学机械与电子控制工程学院,北京100044

出　　处：《原子能科学技术》2023年第1期104-110,共7页Atomic Energy Science and Technology

摘　　要：环形燃料混合堆芯横向流动特性对原堆芯的热工安全具有重要影响。本文基于计算流体力学(CFD)方法建立了3×3环形燃料混合堆芯,通过计算混合堆芯的速度场、局部阻力特性与各组件的出入口流量守恒性,对环形燃料与原堆芯燃料之间的横向流动进行了评价。结果表明,当环形燃料与原堆芯燃料轴向各处阻力一致时,原堆芯燃料出入口冷却剂流量相对偏差小于0.8%,环形燃料出入口冷却剂流量相对偏差小于1.8%,混合堆芯各格架段无显著横向流动。Annular fuel is a new type of pressurized water reactor fuel with inner and outer dual coolant channels.Selecting the actual reactor and annular fuel pilot assembly to form a mixed core to carry out irradiation test is one of the important links in the research and development of annular fuel.Through the operation test in the actual reactor,the structural design and thermal safety performance of the fuel assembly can be fully verified,laying the foundation for the subsequent construction of the annular fuel reactor and engineering applications.The annular fuel mixing core has open flow channels,and the cross flow characteristics have an important impact on the thermal safety of the original core.Therefore,a 3×3 annular fuel mixed core was established based on computational fluid dynamics method.Taking the local resistance characteristics of the two assemblies,the cross velocity field of the mixed core,the flow deviation between inlet and outlet of each assembly in the mixed core,and the flow deviation of each grid section as the evaluation indicators,the cross-flow characteristics of the annular fuel mixed core were analyzed in detail.The results show that the smaller equivalent diameter of the annular fuel outer channel has a retarding effect on the cross flow of the mixed core,so that the deflection effect of the original core mixing vane on the coolant is greatly weakened at the interface of the mixed core assemblies.It effectively eliminates the cross flow caused by the mixing vane.Meanwhile,under the mixed core condition,the coolant flow rate of the original core fuel is only in the 5th,7th,and 9th grid sections,which is smaller than that of the annular fuel,and the rest of the grid sections are larger than the annular fuel.The maximum relative deviation of the flow rate of each spacer grid section in the axial direction is 12%,the average relative deviation of the flow rate in each spacer grid section is about 9%,and the relative deviation of the flow rate between inlet and outlet of each assembly is less

关 键 词：环形燃料 混合堆芯 横向流动特性 计算流体力学 

分 类 号：TL33[核科学技术—核技术及应用]