摘要
主泵轴封应急供水的仿真目的是解决核电厂特殊工况下的培训功能的技术研究。主泵轴封应急供水的功能是在全厂失电、主泵轴封失去供水的特殊情况下,给主泵提供持续的应急轴封注入,以防止反应堆冷却剂通过主泵轴密封泄漏,避免发生LOCA。本文基于现有310MW核电机组的电厂模拟机状态,详细介绍了反应堆主冷却剂泵轴封应急供水的模型仿真过程和运行验证。实现的方法过程包括通过图形化建模平台先模拟出新增管网的模型;对原有模拟机模型程序进行分析,解决原有模拟机不同平台下的不可压缩流体网络矩阵的耦合运算;增加设备操作的人机交互模型;对新增模型里的设备增加盘台界面操作开关按钮画面,对新增模型里的管网增加管网流程图画面;在全厂失电条件下,通过盘台启动主泵轴封应急供水系统,监视新增管网流程图的运行状态等;对更新后的模拟机模型进行运行验证,验证结果表明,主泵轴封应急供水方案实现了在全厂失电条件下,主泵轴封能通过应急供水管网得到有效的冷却,有效的避免了由于主泵轴密封处泄漏而发生LOCA。本项模型升级工作,切实满足了核电厂模拟机培训中对于特殊工况下的培训功能,对流网问题和优化流网模型的算法提供了有效的解决途径。
The simulation purpose for emergency feed water of reactor coolant pump shaft seal is in order to solve technical research for the training function of special condition exercise. The function of reactor coolant pump shaft seal emergency feed water system is to provide emergency continuously injected to the reactor coolant pump shaft seal to prevent the reactor coolant leak through the shaft seal, in the special case of station black out and reactor coolant pump shaft seal lost water supply, avoid the occurrence of LOCA. Based on the present state of simulator in Qinshan nuclear power plant, the model simulation process and operation verification of the reactor coolant pump shaft seal emergency feed water system are introduced in detail in this article. The process of implementation methods including through a graphical modeling platform to simulate the new network model, simulation model of the original simulator procedures for analysis, to solve the incompressible net matrix docking calculation in different platform in original simulator, to create the human interaction model of components operation, add the interface panel graphics of switches,buttons and light for the new modeling components, and increase the new flow chart of the pipe network in the flow diagrams, under the condition of station black out, the reactor coolant pump shaft seal emergency feed water system is started through the panel, and the operation state of the new pipe network flow chart is monitored, and the updated simulator model is verified by running. The verification results show that the emergency feed water program achieve emergency water supply for reactor coolant pump shaft seal at the condition of station black out in the plant, the shaft seal can be effectively cooled, effectively solves the reactor coolant pump shaft seal leak and the occurrence of LOCA.The upgrading of this model effectively meets the needs for improving the training function of special condition exercises during the training of nuclear power plant simulator, and provides an effective way to solve flow net problem and optimize the net model algorithm.
引文