基于一体化三维数值模拟的中国实验快堆冷钠池及其堆内构件热工特性分析  

Thermal Hydraulic Characteristics Analysis on Cold Sodium Pool and Its Internal Components in CEFR based on Three-dimensional Integrated Numerical Calculation

作　　者：张钰浩[1,2] 夏子涵 梁江涛 刘一哲 杨军[3] 叶尚尚[3] 郭忠孝[3] 陆道纲 ZHANG Yuhao;XIA Zihan;LIANG Jiangtao;LIU Yizhe;YANG Jun;YE Shangshang;GUO Zhongxiao;LU Daogang(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,Beijing 102206,China;China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]非能动核能安全技术北京市重点实验室,北京102206 [3]中国原子能科学研究院,北京102413

出　　处：《核科学与工程》2020年第3期499-507,共9页Nuclear Science and Engineering

摘　　要：建立中国实验快堆(CEFR)池式堆本体全尺寸三维模型,进行堆本体冷钠池、热钠池、主容器冷却系统等主要部件的一体化、三维数值计算。通过对热钠池进行部分简化,为冷钠池计算提供更接近实堆运行工况的边界条件,获得CEFR在额定功率稳态工况下冷钠池及其堆内构件三维热工参数,为其结构应力评定及部件设计提供关键输入。计算结果表明:冷钠池内液钠的流动较为复杂,上冷池内流动较为明显;由于冷池中板的阻隔作用,下冷池流动较为微弱。此外,冷钠池内会出现较为明显的热分层现象,使得冷钠池内竖向支承肋板及其堆内构件沿高度方向产生约30℃温差,对其结构强度设计提出更高的要求;主容器冷却系统出口被加热的液钠对上冷钠池的温度、流动分布也有一定影响。本研究为钠冷池式快堆事故安全分析、关键堆内构件结构应力评定及设计提供重要热工输入参数。Three-dimensional full-scale integrated model of the pool-type China Experimental Fast Reactor(CEFR)is established,then the coupled numerical calculation of the hot sodium pool,cold sodium pool,and main vessel cooling system is carried out.The hot sodium pool model is simplified to provide the boundary conditions similar with the prototype reactor operation condition for the accurate simulation of the cold sodium pool.The key three-dimensional thermal parameters of the cold sodium pool and its internal components under the rated power steady state condition are obtained,which provide key input conditions for the structural stress assessment and component design.The results show that the flow behavior in the cold sodium pool is very complex,and the flow intense is more obvious in the upper cold pool.Because of the hindering effect of the middle plate in the cold pool,the flow intense in the lower cold pool is relatively weak.In addition,obvious thermal stratification phenomenon will occur in the cold sodium pool,resulting in approximate 30 ℃ temperature difference along the height direction of the vertical support ribs and the internals within the cold sodium pool,which puts forward higher requirements for its structural strength design.The liquid sodium heated at the outlet of the main vessel cooling system may also influence the temperature distribution of the outside wall in the cold sodium pool.The present work provides significant thermal input parameters for accident safety analysis,structural stress assessment and design of key internals in the pool-type sodium cooled fast reactor.

关 键 词：一体化三维计算 冷钠池 堆内构件 热分层 中国实验快堆 

分 类 号：TL33[核科学技术—核技术及应用]