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DOI:
Journal of ShangHai University of Electric Power :2011,27(6):544-548,553
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AP1000核电站非能动堆芯冷却系统分析及仿真
(上海电力学院电力与自动化工程学院, 上海 200090)
Analysis and Simulation for Passive Safety Reactor Coolant System of The AP1000
(School of Electric Power and Automation Engineering, Shanghai University of Electric Power, Shanghai 200090, China)
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Received:July 04, 2011    
中文摘要: 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.
Abstract: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.
文章编号:20110603     中图分类号:    文献标志码:
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DOI:
Journal of ShangHai University of Electric Power :2011,(6):-
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文章编号:20110603     中图分类号:    文献标志码:
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