钠冷快堆堆外核测量系统热工数值模拟  

Thermal Numerical Simulation of the Ex-core Nuclear Measurement System of Sodium-cooled Fast Reactors

作　　者：孙贤祖 刘兴民[1] 刘林顶[1] SUN Xianzu;LIU Xingmin;LIU Linding(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：《科技资讯》2023年第17期56-60,共5页Science & Technology Information

摘　　要：为验证现有堆外核测量系统通风系统合理性,寻找优化方向,该文利用三维数值模拟方法,对示范快堆堆外核测量系统进行了分析,以研究不同送风参数和不同送风位置下堆外核测量系统内的流场、温度场分布情况。数值模拟结果表明:正常运行工况下送风参数基本满足设计要求,送风位置对冷却效果影响不大,送风温度对核测量系统温度分布的影响大于送风量的影响。计算结果为堆外核测量系统送风系统设计计算提供了依据,为后续一体化快堆相关系统设计提供参考。In order to verify the rationality of the existing ventilation system of the ex-core nuclear measurement system and find the optimization direction,this paper analyzes the ex-core nuclear measurement system of demonstration fast reactors by using the 3D numerical simulation method,so as to study the distribution of the flow field and temperature field in the ex-core nuclear measurement system under different air supply parameters and positions.The numerical simulation results show that air supply parameters basically meet design requirements under normal operating conditions,the air supply position has little effect on the cooling effect,and that the influence of the air supply temperature on the temperature distribution of the nuclear measurement system is greater than that of the air supply volume.The calculation results provide a basis for the design and calculation of the air supply system of the ex-core nuclear measurement system,and provide a reference for the follow-up design of the system related to integrated fast reactors.

关 键 词：CFR600 堆外核测量系统 通风系统 数值模拟 

分 类 号：TL433[核科学技术—核技术及应用]