压水堆核电站给水泵转速控制系统仿真机的研发  被引量:7

Development of simulator for PWR feed-water pump speed control system

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作  者:姚水永 张彦 王潜博 钱明辉[2] 梁军[2] 

机构地区:[1]中广核工程有限公司,广东深圳518124 [2]浙江大学控制科学与工程学系,浙江杭州310027

出  处:《机电工程》2015年第2期251-255,共5页Journal of Mechanical & Electrical Engineering

摘  要:针对核电站仪控调试的成本高和控制参数调试验证工作的不便问题,开发了集成的核电站给水泵控制系统仿真机。介绍了压水堆核电站给水泵转速仿真机的结构、设计方案、主要技术实现和现场应用。利用Lab VIEW程序开发了热工水力模型,采用西门子的PLC实现了仿真机与核电厂DCS、仿真机与给水泵控制箱的连接,利用Win CC-flexible工业组态软件编辑了友好的人机界面,设置了实时数据库存储运行数据,借助OPC通讯协议完成了系统内部的实时通讯,由多个技术部件一起构成了压水堆核电站转速控制仿真平台。进行了启停泵试验、阶跃升转速和手动操作试验。测试结果表明,该平台能够较好地模拟系统瞬态工况和稳态工况,可用于相关技术培训和核电站仪表控制系统的参数优化。Aiming at reducing the cost of I&C commissioning and control parameter verification in nuclear power plant, an integrated pump control system simulator was developed. The structure and design of the pump speed control simulator, the main technology and field applications were introduced. The thermal-hydraulic model was developed based on LabVIEW. Siemens PLC was used to connect the simulator and DCS in the nuclear power plant. WinCC-flexible industrial configuration software was used to edit the friendly interface, real-time database was used to store operational data set. The system real-time communication was realized based on OPC communication protocol. All these technologies constitute a real simulator. The starting and stopping the pump test, rank jumped speed test and manual test were proceeded. The test results indicate that it has a good simulation effect. It can be used to verify parameters, do nuclear-related technology training and optimize the control system.

关 键 词:压水堆核电站 仿真机 给水泵 转速控制 LABVIEW OPC 

分 类 号:TP273[自动化与计算机技术—检测技术与自动化装置] TH39[自动化与计算机技术—控制科学与工程]

 

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