AP1000核电站非能动堆芯冷却系统分析及仿真  

Analysis and Simulation for Passive Safety Reactor Coolant System of The AP1000

作　　者：钱虹[1] 辛浩[1] 秦士民[1] 

机构地区：[1]上海电力学院电力与自动化工程学院,上海200090

出　　处：《上海电力学院学报》2011年第6期544-548,553,共6页Journal of Shanghai University of Electric Power

摘　　要：分析了AP1000核电站的非能动堆芯冷却系统的组成,并对其子系统的监控界面和触发逻辑组态进行了仿真,形成了一套对系统及触发逻辑的整体测试方案.The composition, the passive and trigger logic of the Passive Safety Reactor Coolant system to the introduced Westinghouse AP1000 nuclear power plant is analyzed. And the system flow and trigger logic of its sub-system is simulated entirely, forming the system and trigger entire test strategy.

关 键 词：非能动 堆芯冷却系统 自动降压系统 安全注水系统 

分 类 号：TM623[电气工程—电力系统及自动化]