第34卷第2期 2014年6月
核科学与工程
Nuclear Science and Engineering
Vol.34No.2
Jun.2014
热工水力子通道分析程序ATHAS自
的稳态验证
刘伟1,2，朱元兵3，白宁3，单建强1，张博1，苟军利1，厉井钢3（1.西安交通大学核科学与技术学院，西安，710049；
2.中国核动力研究设计院，核反应堆系统设计技术国家级重点实验室，成都，610041；
3.中科华核电技术研究院，深圳，518026）
摘要：利用具有自主知识产权的子通道程序ATHAS对GE3X3组件进行稳态计算，并将ATHAS的预测值与实验测量值及其他子通道程序的预测值进行了对比分析，结果表明：ATHAS能够准确预测 GE3X3组件内的热工水力参数分布，展示了ATHAS可靠的物理模型。本文对ATHAS进行稳态验
证的思路和方法，对我国核电站热工水力软件自主化的设计开发具有借鉴意义。关键词：子通道分析程序ATHAS;GE3X3组件；稳态验证
中图分类号：TL333
文章标志码：A
文章编号：0258-0918(2014)02-0187-06
Steady-state Verification of Thermal-hydraulics
Sub-channelAnalysisCodeATHAS
LIUWeil",ZHU Yuan-bing",BAINing",SHAN Jian-qiang'，
ZHANG Bo',GOU Jun-li',LI Jinggang
(1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
2. State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610041, China
3. China Nuclear Power Technology Research Institute, Shenzhen 518026, China
Abstract:GE3 X 3 test bundle experiments were simulated with sub-channel analysis code ATHAS.Comparisons of the obtained results by ATHAS code with the experimental measurements and other sub-channel codes show that ATHAS is capable to predict thermal-hydraulic parameters distribution in GE3X3 components accurately All of this demonstrates the reasonable physical models and powerful application functions of ATHAS. The work of this thesis can be taken example by the design and development of thermal-hydraulic program of nuclear power plant in China.
Key words:sub-channel code ATHAS; GE3X3 bundle; steady-state verification 收稿日期：2014-01-21；修回日期：2014-02-28
伟(1989--），男，陕西强安人，硕士研究生，现主要从事反应堆热工水力与安全分析研究
作者介：刘
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