摘要
采用点堆中子动力学模型、两相漂移流蒸汽发生器模型、三区不平衡稳压器模型、主循环泵四象限特性模型和非能动应急余热导出系统模型,并利用Compaq Visual Fortran 6.0语言开发了微机型压水反应堆瞬态热工水力特性分析程序,并利用Microsoft Visual Studio.NET语言实现输入参数的可视化、输出结果的实时处理和动态显示。利用RELAP5程序对本瞬态安全分析软件进行了可靠性验证,结果表明,本软件求解精度较高、速度快、界面新颖、功能完善、可操作性强。此外,利用本软件对秦山核电站事故瞬态工况下的热工水力特性进行了分析,得出了一些具有工程价值的结论。
A point reactor neutron kinetics model,a two-phase drift-flow U-tube steam generator model,an advanced non-equilibrium three regions pressurizer model,and a passive emergency core decay heat-removed system model are adopted in the paper to develop the computerized analysis code for PWR transient thermal-hydraulic characteristics,by Compaq Visual Fortran 6.0 language.Visual input,real-time processing and dynamic visualization output are achieved by Microsoft Visual Studio.NET language.The reliability verification of the soft has been conducted by RELAP 5,and the verification results show that the software is with high calculation precision,high calculation speed,modern interface,luxuriant functions and strong operability.The software was applied to calculate the transient accident conditions for QSNP,and the analysis results are significant to the practical engineering applications.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2010年第2期47-49,62,共4页
Nuclear Power Engineering
关键词
压水堆
核动力系统
瞬态特性
输入可视化
动态显示
PWR
Nuclear power system
Transient characteristics
Visual input
Dynamic visualization