一体化核反应堆套管管束式换热器设计与试验  

Design and tests of a double-tube bundle heat exchanger for an integrated nuclear reactor

作　　者：陈明辉[1] 厉日竹[1] 何晓艳[1] 刘俊强[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2006年第12期2065-2068,共4页Journal of Tsinghua University(Science and Technology)

基　　金：国家"211"工程建设项目

摘　　要：建立了套管管束式换热器的计算模型，以便进行该种换热器热工水力学设计计算和结构优化。利用该模型，研．究了一体化核反应堆自然循环和强迫循环两种工况下该换热器的比表面、传热系数、体积比功率等特性，确定了优化方向。以自然循环工况下，管心距为15．8～16．4mm时，该换热器特性最优的分析结果为依据。加工了19根传热管组件的实验本体，在清华大学核能与新能源技术研究院进行了相关的热工水力学试验。试验所得传热系数，阻力降在未引入任何经验常数的情况下。分别与计算结果偏差小于5％、10％。An analytical model of thermal-hydraulic design and structural optimization was developed for a double-tube bundle heat exchanger of an integrated nuclear reactor. The method considered the surface heat flows, the heat transfer coefficient, the power density, and other characteristics of the heat exchanger for natural circulation or forced circulation. A 19-module heat exchanger was designed based on the conclusion that center distances between 15.8 mm and 16. 4 mm are better for natural circulation. Thermal-hydraulic experiments show that the error of the predicted heat transfer coefficients is less than 5%, while the error of the pressure drop is less than 10%.

关 键 词：一体化核反应堆 自然循环 套管管束式换热器 热工水力学设计 

分 类 号：TL353.13[核科学技术—核技术及应用]