压水堆核动力系统瞬态热工水力特性分析仿真软件
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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.
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.
引文
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[7]秋穗正,郭玉君,张金玲,等.蒸汽发生器瞬态特性分析的数学模型[J].西安交通大学学报,1995,29:113～117.
[8]苏光辉,郭玉君,张金玲,等.非能动堆芯余热排出系统自然循环特性研究[J].西安交通大学学报,1995,29:38～43.
[9]郭玉君.核动力系统热工水力分析程序的研制与应用[D].西安:西安交通大学博士学位论文,1994.
[10]熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,1:20～33.
[11]唐宗渝.余热排出系统冷却丧失事故[J].核科学与工程,1990,3:237～264.
[12]韩良弼,张明.秦山核电厂蒸汽发生器及其内件的地震分析[J].核科学与工程,1991,4:308～317.
[2]Redfield J A,Prescop V,Margolis S G.Pressurizer Pe-rformance During Loss of Load Tests at Shippingport:Analysis and Test[J].Nuclear Applications.1968,4:173～181.
[3]Baron R C.Digtial Simulation of a Nuclear Pressurizer[J]Nuclear Science and Engineering.1973,52:283～291.
[4]Abdallah A M,Mariy A H,Rabie M A.Pressurizer Tran-sients Dynamic Model[J].Nuclear Engineering and De-sign.1982,73:447～453.
[5]Baggovra B,Martin W R.Transient Analysis of the Three-Mile Island Unit 2 Pressurizer System[J].Nuclear Technology.1983,62:407～416.
[6]Beak S M.A Non-Equilibrium Three Region Model for Transient Analysis of Pressurized Water Reactor Pressur-izer System[J].Nuclear Technology.1986,74:213～221.
[7]秋穗正,郭玉君,张金玲,等.蒸汽发生器瞬态特性分析的数学模型[J].西安交通大学学报,1995,29:113～117.
[8]苏光辉,郭玉君,张金玲,等.非能动堆芯余热排出系统自然循环特性研究[J].西安交通大学学报,1995,29:38～43.
[9]郭玉君.核动力系统热工水力分析程序的研制与应用[D].西安:西安交通大学博士学位论文,1994.
[10]熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,1:20～33.
[11]唐宗渝.余热排出系统冷却丧失事故[J].核科学与工程,1990,3:237～264.
[12]韩良弼,张明.秦山核电厂蒸汽发生器及其内件的地震分析[J].核科学与工程,1991,4:308～317.
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