CEFR改进型独立热交换器热工水力分析研究  

Thermal Hydraulics Analysis for Modified Sodium-to-sodium Decay Heat Exchanger of CEFR

作　　者：陈祖国[1] 许义军[1] CHEN Zu-guo XU Yi-jun(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：《核科学与工程》2016年第4期441-448,共8页Nuclear Science and Engineering

摘　　要：事故余热排出系统是池式钠冷快堆最重要的专设安全设施之一,是实现反应堆相关事故工况下余热排出安全功能的主要手段,如全厂断电工况,而独立热交换器是快堆事故余热排出系统的关键设备之一。本文以ANSYS FLUENT为工具,对中国实验快堆现有的独立热交换器和一种改进的新型独立热交换器布置在快堆热池中的情况进行了瞬态数值模拟,并分析比较其结果,证明了改进型独立热交换器在热工水力上的可行性。本文工作对大型快堆的独立热交换器的设计具有一定的借鉴意义。Decay heat removal system is one of principal engineered safety features of pool-type sodium-cooled fast reactor,it is a main way to carry out the safety function of decay heat remove under some accident conditions for the reactor,such as reactor scram condition,and one of the key equipment of decay heat removal system for fast reactor is sodium-to-sodium decay heat exchanger（DHX）.We use the ANSYS FLUENT software to run transient numerical simulations of the DHX in CEFR and the new modified DHX which is setup in hot pool of fast reactor.Through comparing the simulation results,the feasibility of the modified DHX design is demonstrated in terms of thermal hydraulics performance.The numerical analysis results are important reference to the design of DHX for large-type size fast reactor.

关 键 词：快堆 热交换器 热工水力 数值模拟 

分 类 号：TL33[核科学技术—核技术及应用]