压水堆核电厂一回路仿真可视化研究
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摘要
对压水堆核电厂一回路系统及主要设备进行了详细分析,建立了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和主循环泵四象限特性模型,并以此为基础使用FORTRAN90语言和Visual C++语言通过混合编程的方法开发了核电厂仿真分析程序,实现了对压水堆核电厂一回路主要设备及全系统的可视化仿真计算。软件提供实时绘图、缩放等可视化功能,还提供了数据结果的标准图片格式和标准文本格式输出。通过将程序的计算结果与RELAP5/MOD3.0计算结果进行比较,对程序的可靠性进行了验证。
In this study the main equipments and the primary loop of PWR nuclear power plant(NPP) were analyzed in detail.The model of point neutron dynamics,steam generator model with two-phase drift-flux governing equations,3-zone non-equilibrium pressurizer model and 4-quadrant main pump performance model were established.Based on the above models,a NPP simulation program was developed by using mixed programming with FORTRAN90 and Visual C++.The simulation program is of capability to achieve visualized simulation for the main equipments in primary loop and entire system of PWR nuclear power plant.It provides not only the visualized functions of real-time plotting,zooming,etc.,but also the output of numerical results with standard picture and/or text formatting files.Besides,the program was validated by comparing the calculation results of the program developed by authors and those of RELAP5/MOD3.0.
In this study the main equipments and the primary loop of PWR nuclear power plant(NPP) were analyzed in detail.The model of point neutron dynamics,steam generator model with two-phase drift-flux governing equations,3-zone non-equilibrium pressurizer model and 4-quadrant main pump performance model were established.Based on the above models,a NPP simulation program was developed by using mixed programming with FORTRAN90 and Visual C++.The simulation program is of capability to achieve visualized simulation for the main equipments in primary loop and entire system of PWR nuclear power plant.It provides not only the visualized functions of real-time plotting,zooming,etc.,but also the output of numerical results with standard picture and/or text formatting files.Besides,the program was validated by comparing the calculation results of the program developed by authors and those of RELAP5/MOD3.0.
引文
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[11]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,1994.
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[13]熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,9(1):20-33.XIONG Jian,FU Longzhou.Dynamic modellingand simulation of a nuclear steam generator[J].Nuclear Science and Engineering,1989,9(1):20-33(in Chinese).
[14]唐宗渝.余热排出系统冷却丧失事故[J].核科学与工程,1990,10(3):237-264.TANG Zongyu.The loss of cooling event of de-cay heat removal system[J].Chinese Journal ofNuclear Science and Engineering,1990,10(3):237-264(in Chinese).
[15]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,1991,11(4):308-317.HAN Liangbi,ZHANG Ming.Seismic analysisof steam generator and its internals for QinshanNPP[J].Chinese Journal of Nuclear Science andEngineering,1991,11(4):308-317(in Chi-nese).
[2]苏云,许以全,曹学武,等.SCDAP/RELAP5程序结构及严重事故有关的模型概述[J].核动力工程,2003,24(6S2):51-55.SU Yun,XU Yiquan,CAO Xuewu,et al.Codestructure and severe accident-related models ofSCDAP/RELAP5 MOD3program[J].NuclearPower Engineering,2003,24(6S2):51-55(inChinese).
[3]SUMMERS R M,COLE R K,SMITH R C,etal.MELCOR computer code manuals:Primerand user’s guides,Version 1.8.3[M].US:NRC,1995.
[4]McFADDEN J H.RETRAN-02:A program fortransient thermal-hydraulic analysis of complexfluid flow systems,Volume 3:User’s manual,NP-1850-CCM[R].Palo Alto:Electric PowerResearch Institute,1981.
[5]王子才.仿真技术发展及应用[J].中国工程科学,2003,5(2):40-44.WANG Zicai.Development and application ofsimulation technology[J].Engineering Sciences,2003,5(2):40-44(in Chinese).
[6]朱永利.法国电力系统仿真机考察情况介绍[J].电力情报,1995,11(1):19-21.
[7]吕崇德,睦喆,姜学智.仿真技术在中国电力工业中的发展及应用[J].系统仿真学报,1999,11(4):224-227.LU Chongde,SUI Zhe,JIANG Xuezhi.Devel-opment and application of simulation technologiesin the power industry of China[J].Journal ofSystem Simulation,1999,11(4):224-227(inChinese).
[8]GHIAASIAAN S M,WASSEL A T,FARR JL,et al.Heat conduction in nuclear fuel rods[J].Nuclear Engineering and Design,1985,85(1):89-96.
[9]BEAK S M.A non-equilibrium three regionmodel for transient analysis of pressurized waterreactor pressurizer system[J].Nucl Technol,1986,74(3):213-221.
[10]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(5):113-117.QIU Suizheng,GUO Yujun,ZHANG Jinling,etal.A mathematical model for transient analysisof steam generator[J].Journal of Xi’an JiaotongUniversity,1995,29(5):113-117(in Chinese).
[11]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,1994.
[12]袁兆鼎.刚性常微分方程初值问题数值解法[M].北京:科学出版社,1987:63-75.
[13]熊健,付龙舟.核蒸汽发生器建模及其仿真[J].核科学与工程,1989,9(1):20-33.XIONG Jian,FU Longzhou.Dynamic modellingand simulation of a nuclear steam generator[J].Nuclear Science and Engineering,1989,9(1):20-33(in Chinese).
[14]唐宗渝.余热排出系统冷却丧失事故[J].核科学与工程,1990,10(3):237-264.TANG Zongyu.The loss of cooling event of de-cay heat removal system[J].Chinese Journal ofNuclear Science and Engineering,1990,10(3):237-264(in Chinese).
[15]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,1991,11(4):308-317.HAN Liangbi,ZHANG Ming.Seismic analysisof steam generator and its internals for QinshanNPP[J].Chinese Journal of Nuclear Science andEngineering,1991,11(4):308-317(in Chi-nese).
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