核电厂重要的核辅助系统建模研究及应用
摘要
核电的安全性和经济性始终是人们关注的问题。为了保证核电厂的安全性、提高经济性,计算机和控制、信息技术正越来越多地被应用于核电领域。这其中的主要体现就是计算机仿真技术和数字化仪控技术在核电站的应用。
本论文以扩展核电站安全分析对象范围为目标,围绕核电站辅助系统流体网络计算分析问题,针对CPR1000型核电站,进行了单相流体网络的热工水力数值模拟与计算分析研究。首先以化学和容积控制系统和硼和水补给系统为对象,进行了详细的系统流程分析,在此基础上进行了简化,得到具体的研究对象。其次,将复杂的系统对象拆分成不同的基本部件,分析并建立了相应的数学模型。最后通过对系统设计数据的收集和转换,使用Flowmaster软件,将各部件组合形成了详细的辅助系统流体网络模型。
本文针对含有热工流体网络模型的压水堆核电站核辅助系统建立仿真模型,构成了较完整的虚拟电厂核辅助系统的热工流网模型,根据实际电厂正常运行过程中所发生的瞬态工况进行实时模拟计算。并将计算结果与电厂实际运行过程中曲线对比,验证了系统模型在瞬态工况下的工作状况。
Safety and economy efficiency of Nuclear Power Plant is always concerned by people. In order to enhance the safety and economy of Nuclear Power Plant, computer and control-info-technology is widely applied in nuclear power field. One of the main embodiment is the application of simulation technology and digitizer control technology in Nuclear Power Plant.
The nuclear power plant simulation and security analysis aimed at one loop-one and loop-two. First, this paper is to extend the range of nuclear security analysis of the object as the goal of fluid around the nuclear power plant auxiliary systems analysis of network computing problems for CPR1000 Nuclear Power Plant. The study is conducted on a single-phase fluid network of thermal-hydraulic analysis of numerical simulation and calculation. According to REA and RCV as objects, the simplified models are built up. After a detailed analysis, the objects are decided. Second, complicated systems split into different basic components. The corresponding mathematical models of these components are established. Then it is time to collect the detailed data and transform them into a useful form. Using Flowmaster software, the components are combined to form a detailed supporting fluid network models.
According to these built models, a thermal fluid network model of t auxiliary system is built up. Based on the actual power plants occurred during the normal operation of the transient conditions in real-time simulation. The calculated results with the actual power plant during operation curves to verify the system model in transient operating conditions of the working conditions. Finally, the conclusions are given.
本论文以扩展核电站安全分析对象范围为目标,围绕核电站辅助系统流体网络计算分析问题,针对CPR1000型核电站,进行了单相流体网络的热工水力数值模拟与计算分析研究。首先以化学和容积控制系统和硼和水补给系统为对象,进行了详细的系统流程分析,在此基础上进行了简化,得到具体的研究对象。其次,将复杂的系统对象拆分成不同的基本部件,分析并建立了相应的数学模型。最后通过对系统设计数据的收集和转换,使用Flowmaster软件,将各部件组合形成了详细的辅助系统流体网络模型。
本文针对含有热工流体网络模型的压水堆核电站核辅助系统建立仿真模型,构成了较完整的虚拟电厂核辅助系统的热工流网模型,根据实际电厂正常运行过程中所发生的瞬态工况进行实时模拟计算。并将计算结果与电厂实际运行过程中曲线对比,验证了系统模型在瞬态工况下的工作状况。
Safety and economy efficiency of Nuclear Power Plant is always concerned by people. In order to enhance the safety and economy of Nuclear Power Plant, computer and control-info-technology is widely applied in nuclear power field. One of the main embodiment is the application of simulation technology and digitizer control technology in Nuclear Power Plant.
The nuclear power plant simulation and security analysis aimed at one loop-one and loop-two. First, this paper is to extend the range of nuclear security analysis of the object as the goal of fluid around the nuclear power plant auxiliary systems analysis of network computing problems for CPR1000 Nuclear Power Plant. The study is conducted on a single-phase fluid network of thermal-hydraulic analysis of numerical simulation and calculation. According to REA and RCV as objects, the simplified models are built up. After a detailed analysis, the objects are decided. Second, complicated systems split into different basic components. The corresponding mathematical models of these components are established. Then it is time to collect the detailed data and transform them into a useful form. Using Flowmaster software, the components are combined to form a detailed supporting fluid network models.
According to these built models, a thermal fluid network model of t auxiliary system is built up. Based on the actual power plants occurred during the normal operation of the transient conditions in real-time simulation. The calculated results with the actual power plant during operation curves to verify the system model in transient operating conditions of the working conditions. Finally, the conclusions are given.
引文
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[24]张兆顺,崔桂香.流体力学[M].北京:清华大学出版社. 1999.
[25]黄成云.阀门工艺技术手册[M].北京:机械工业出版社. 2009.
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[33] Defining initiating events for purposes of probabilistic safety assessment. IAEA, 1993.
[2]张睿,邹林,汪永平.广泛利用核能积极应对全球气候变化[J].中国核工业,2007,(08):17~20.
[3]邬国伟.核反应堆工程设计[M].原子能出版社,1997.
[4]安玉祥. DCS在火电厂的应用与发展[J].电力建设,2003,(11):37~39.
[5]王兵树,高建强,马良玉.火电机组仿真器技术及其发展方向研究[J].华北电力大学学报, 2001, (03):83~87.
[6]刘艳,顾雪平,卢锦玲,等.真分散控制系统在线式多功能电站仿真机的设计与实现[J].电力系统自动化, 2003, (12):78~80.
[7]林萌.分布式并行实时核动力仿真分析系统的研发及应用[D].上海:上海交通大学, 2006.
[8]高蕊,杨燕华,林萌.基于系统程序的压水堆核电厂热力系统建模[J].核动力工程, 2007, 28期.
[9]张占龙,罗辞勇,何为.虚拟现实技术概述[J].计算机仿真,2005,2期
[10]史觊,蒋明瑜,马云青.核电站仪控系统数字化开发仿真测试技术研究[J].核技术,2005,28(02):163~168.
[11]朱继洲.压水堆核电厂的运行[M].北京:原子能出版社, 2000, 201~224.
[12]濮继龙,等.大亚湾核电站运行教程.深圳:原子能出版社, 1998.
[13] D. S. Miller. Internal Flow Systems.1992.
[14] M. H. Chaudhry. Applied Hydraulics Transients [M]. Van Nostrand Reinhold Company, 1979.
[15] E. B. Wylie and V. L. Streeter. Fluid Transients[M].FEB Press, 1982.
[16] J. Parmakian. Waterhammer Analysis[M].1978.
[17] Flowmaster Reference Version 7.5 Help, www.Flowmaster.com.
[18] Flowmaster Version 7.5 Help, www.Flowmaster.com.
[19] Flowmaster7.5 Reference Help, Version 7, 2008.
[20]王正中.系统仿真技术[M].科学出版社,北京,1986.
[21]班克斯等著.肖田元,范文慧译.离散事件系统仿真[M].机械工业出版社, 2007.
[22]高润田.单相可压缩流体网络的数学模型及仿真算法研究[东南大学硕士论文]. 2000.
[23]马辉迎,电站模块化模型开发及流体网络的建模方法[清华大学博士学位论文]. 1990.
[24]张兆顺,崔桂香.流体力学[M].北京:清华大学出版社. 1999.
[25]黄成云.阀门工艺技术手册[M].北京:机械工业出版社. 2009.
[26]华北电力学院.离心水泵[M].北京:水利水电出版社. 1983.
[27]关醒凡.泵的理论与设计[M].北京:机械工业出版社. 1987.
[28]李世煌,吴桐林.水泵设计教程[M].北京:机械工业出版社. 1990.
[29]施卫东.流体机械[M].成都:西南交通大学出版社. 1996.
[30]朱聘冠.换热器原理及计算[M].北京:清华大学出版社. 1987.
[31]解增忠,张俊峰.管壳换热器模型库及在换热网络仿真中的应用[J].系统仿真学报2005.12.
[32]吴靖,孙国基.化工过程仿真培训系统中的换热器模型[J].计算机仿真,第13卷4期.
[33] Defining initiating events for purposes of probabilistic safety assessment. IAEA, 1993.