压水堆稳态系统程序开发  

Development of Steady System Program for Pressurized Water Reactor

作　　者：习蒙蒙 初晓[1] 蔡容 XI Meng-meng;CHU Xiao;CAI Rong(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu Sichuan 610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室

出　　处：《科技视界》2019年第30期4-7,42,共5页Science & Technology Vision

摘　　要：针对一体化压水堆的具体结构,建立合理的系统模型,利用FORTRAN90语言开发了系统稳态计算程序。利用本程序对满功率强迫循环和30%功率自然循环稳态运行工况下的热工水力特性进行了分析,得到了蒸汽发生器套管段一二次侧冷却剂和换热管内温度沿轴向高度的分布,冷却剂及燃料元件温度沿堆芯轴向的分布等结果,并利用RELAP5程序进行验证,证明了本程序的可靠性。本程序可以作为一体化压水堆系统的热工水力方案设计,也可用于系统的运行和安全管理。A reasonable system model was established in the paper to develop the steady thermal-hydraulic analysis code for the integral pressurized water reactor, by FORTRAN90 language. Using the steady analysis code, the steady-state thermal-hydraulic characteristics of both forced circulation and natural circulation are presented in this dissertation.The temperature distribution along the axial height of the coolant, steam generator tubes and fuel elements were obtained. At the same time, the simulated results of the steady analysis code were compared with those of RELAP5 and a good agreement was obtained. The steady analysis code provides important theoretical base for the design,operation and security management of integral pressurized water reactor.

关 键 词：一体化压水堆 稳态计算 热工水力 

分 类 号：TL421.1[核科学技术—核技术及应用]