核电厂数字化I&C系统关键技术研究现状及发展策略  被引量:14

Status and Development Tactics for Key Technology of Digitizedlnstrument and Control System for Nuclear Power Plant

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作  者:杨岐[1] 

机构地区:[1]中国核动力研究设计院,成都610041

出  处:《核动力工程》2002年第A02期66-69,共4页Nuclear Power Engineering

摘  要:国外的核电厂数字化仪表与控制(I&C)系统已经取得显著成绩,我国尚处在起步阶段。中国核动力研究设计院采用国内外成熟的工业控制技术和设备研究开发出数字化反应堆保护系统样机、数字化反应堆控制系统样机、先进控制室研究开发平台、高精度实时核蒸汽供应系统仿真机及相关的17个计算机软件,获得了进一步研究开发的经验,具备了中外合作研制核电厂数字化I&C系统的条件,也为在新一代压水堆核电厂实现数字化I&C系统国产化奠定了坚实基础。The research of nuclear power plant digitized instrument and control system (I&C) in foreign countries has been achieved remarkable success, but China has just started the research in that field. The research results has been developed by Nuclear Power Institute of China (NPIC) adopting mature industry control technologies and facilities. These results include the prototypes of the digitized reactor protection system and the digitized reactor control system, the platform used for the advance control room, the high-precision real-time simulator for the nuclear steam supply system, and the related 17 computer software. Through these development activities, research experience is accumulated, conditions for international cooperation is achieved. This also set enhanced technology basis for realizing self -reliance of nuclear power plant digitized instrument and control system (I&C).

关 键 词:数字化I&C系统 核电厂 控制系统 数字化仪表 反应堆 

分 类 号:TM623[电气工程—电力系统及自动化] TP216[自动化与计算机技术—检测技术与自动化装置]

 

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