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国内三代EPR核电常规岛仪控设计技术特点和比较 被引量:1

Technical feature and comparison of the instrument control design of domestic third-generation EPR nuclear conventional island
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摘要 我国目前在建的台山核电站采用了欧洲压水堆(European pressurized water reactor,EPR)三代核电技术。与CPR1000核电工程相比,EPR机组使用了全新的仪控设计特性。文章描述了台山结构核电站工程常规岛的仪控设计特性和结构,着重进行了与CPR1000工程常规岛仪控设计的特性比较和背景分析。对应的比较和分析主要集中于如下几个方面:通用仪控平台;测点设置原则的变化;DCS逻辑设计平台;DCS设计文件分工;仪控设备供电要求的变化;DCS机柜布置和电缆设计接口的变化。 The Taishan Nuclear Power plant under construction adopts European pressurized water reactor (EPR).Compared to CPR1000,the EPR has new instrumentation and control design feature.This paper describes conventional island instrumentation and control architecture and feature of Taishan nuclear power plant, especially focuses on the related comparison with the CPR1000 project with the background analysis.The analysis focuses mainly on the following areas:general instrumentation and control plaffom;the measurement point configuration;DCS logic design platform;DCS design scope partition;instrumentation and control control equipment power supply configuration; DCS cabinet allocation and cable route interface.
作者 王小博
出处 《企业技术开发》 2011年第11期38-40,45,共4页 Technological Development of Enterprise
关键词 欧洲压水堆(EPR) 常规岛 仪控设计 CPR1000 DCS设计 European pressurized water reactor (EPR) conventional island instrumentation and control design CPR1000 DCS design
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  • 5罗必雄,乔旭斌,陈娟,徐翔.国内三代EPR核电常规岛技术特点[J].电力建设,2010,31(9):102-106. 被引量:7

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