AP1000核电站非能动堆芯冷却系统分析及仿真

钱虹; 辛浩; 秦士民

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上海电力大学学报: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

钱虹, 辛浩, 秦士民

(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

QIAN Hong, XIN Hao, QIN Shi-min

(School of Electric Power and Automation Engineering, Shanghai University of Electric Power, Shanghai 200090, China)

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本文已被：浏览 1468次下载 1887次
投稿时间：2011-07-04

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.

中文关键词: 非能动堆芯冷却系统自动降压系统安全注水系统

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.

keywords: passive reactor coolant system automatic depressurization system safety injection system

文章编号：20110603 中图分类号： 文献标志码：

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作者	单位	E-mail
钱虹	上海电力学院电力与自动化工程学院, 上海 200090	sh@163.com
辛浩	上海电力学院电力与自动化工程学院, 上海 200090
秦士民	上海电力学院电力与自动化工程学院, 上海 200090

Author Name	Affiliation	E-mail
QIAN Hong	School of Electric Power and Automation Engineering, Shanghai University of Electric Power, Shanghai 200090, China	sh@163.com
XIN Hao	School of Electric Power and Automation Engineering, Shanghai University of Electric Power, Shanghai 200090, China
QIN Shi-min	School of Electric Power and Automation Engineering, Shanghai University of Electric Power, Shanghai 200090, China

引用文本：
钱虹,辛浩,秦士民.AP1000核电站非能动堆芯冷却系统分析及仿真[J].上海电力大学学报,2011,27(6):544-548,553.
QIAN Hong,XIN Hao,QIN Shi-min.Analysis and Simulation for Passive Safety Reactor Coolant System of The AP1000[J].Journal of Shanghai University of Electric Power,2011,27(6):544-548,553.