核电站风管放射性气体活度数字监测系统设计
发布时间:2019-01-11 07:33
【摘要】:目前,国内核电站风管放射性气体活度监测系统基本上都采用国外成熟产品,有必要对其进行自主开发。系统设计从系统设计要求、主要技术指标入手,主要开展硬件(包括信号输入输出接口、PLC模块以及HMI等)设计和软件(软件平台、状态参数监控单元流程等)设计,同时开展性能测试和相关问题讨论。结果表明:本次自主开发的核电站风管监测系统与国外成熟产品水平相当,系统具有高可靠性,高稳定性和较强的系统接口能力,可适用于各类核电厂的需求。
[Abstract]:At present, the domestic nuclear power plant air duct radioactive gas activity monitoring system basically uses the foreign mature product, it is necessary to carry on the independent development to it. The system design starts with the system design requirements and main technical specifications, and mainly develops the design of hardware (including signal input and output interface, PLC module and HMI etc.) and software (software platform, state parameter monitoring unit flow, etc.). At the same time, the performance test and related issues are discussed. The results show that the self-developed air duct monitoring system for nuclear power plants is of the same level as foreign mature products, and the system has high reliability, high stability and strong system interface capability, which can be applied to the demand of various nuclear power plants.
【作者单位】: 中科华核电技术研究院;
【分类号】:TM623;TP274
[Abstract]:At present, the domestic nuclear power plant air duct radioactive gas activity monitoring system basically uses the foreign mature product, it is necessary to carry on the independent development to it. The system design starts with the system design requirements and main technical specifications, and mainly develops the design of hardware (including signal input and output interface, PLC module and HMI etc.) and software (software platform, state parameter monitoring unit flow, etc.). At the same time, the performance test and related issues are discussed. The results show that the self-developed air duct monitoring system for nuclear power plants is of the same level as foreign mature products, and the system has high reliability, high stability and strong system interface capability, which can be applied to the demand of various nuclear power plants.
【作者单位】: 中科华核电技术研究院;
【分类号】:TM623;TP274
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