核电蒸汽发生器热工水力分析程序研究现状与进展  

Introduction on the Thermal-hydraulic Analysis Codes for Nuclear Steam Generator

作　　者：姚彦贵[1] 祖洪彪[1] 姚伟达[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核安全》2015年第1期85-94,共10页Nuclear Safety

基　　金：国家科技重大专项CAP1400蒸汽发生器及其关键部件性能试验;课题编号2011zx06002-020

摘　　要：本文介绍了核电蒸汽发生器几种典型的热工水力分析程序,阐述了一维稳态热工水力分析程序GENF、一维瞬态热工水力分析程序TRANFLOW和三维稳态/瞬态热工水力分析程序ATHOS的分析模型、原理和功能应用,介绍了这三种程序的试验验证和实堆验证情况,并分析了我国核电蒸汽发生器热工水力分析程序的现状与进展。This paper describes several typical steam generator thermal-hydraulic analysis programs. Three thermal hydraulic code analysis model,principles and functions of the application are introduced. GENF is a one-dimensional code for steady state analysis,and another one-dimensional code TRANFLOW is used for transients,while ATHOS is a three-dimensional code which can be used to deal with steady as wall as transient analysis. And the code test verification and actual operating parameters verify situations are described. At last,the status and development of SG thermal-hydraulic analysis codes in China are analyzed.

关 键 词：热工水力 蒸汽发生器 分析程序 核电 

分 类 号：TL35[核科学技术—核技术及应用]