摘要
为有效跟踪核电厂瞬态事件和事故,以及监视事故后的过程状态,核电厂需在主控室房间设置专用的事故后监视系统(PAMS)。通过PAMS人机接口显示核电厂事故后参数和设备,为操作员提供监视与记录界面,尤其涉及三道安全屏障的反应性控制、反应堆堆芯冷却和一回路系统的热导出、放射性物质的相关参数和设备信息。依据核电厂安全参数显示的相关标准,结合华龙一号防城港3^(#)、4^(#)机组安全级仪控系统总体架构设计,阐述了PAMS设计和实现的过程。相较于以往硬显示的实现方案,提出了一种基于F-SC1等级的FirmSys数字化平台实现事故后监视功能的设计方案。目前,该方案已在防城港3#机组完成现场热态调试投入实际应用,可为后续核电厂事故后监视功能提供方案借鉴与参考。
To effectively track transient events and accidents in nuclear power plants and monitor the process status after accidents,special post-accident monitoring system(PAMS)should be installed in the main control room.PAMS man-machine interface is used to display the parameters and equipment after nuclear power plant accident,providing monitoring and recording interface for operators,especially involving the reactivity control of three safety barriers,reactor core cooling and thermal export of primary circuit system,and related parameters and equipment information of radioactive substances.According to the relevant standards of nuclear power plant safety parameter display,combined with the overall architecture design of safety level instrument control system of Hualong No.1 Fangchenggang No.3 and No.4 unit,the design and implementation process of PAMS is described.Compared with the previous hard display implementation scheme,the design scheme of FirmSys digital platform based on F-SC1 level for post-accident monitoring is proposed.At present,the scheme has been put into practical application in Fangchenggang No.3 unit for on-site thermal commissioning,which can provide a reference for post-accident monitoring of nuclear power plants.
作者
王志嘉
孙月亮
孙洪涛
夏利民
WANG Zhijia;SUN Yueliang;SUN Hongtao;XIA Limin(China Techenergy Co.,Ltd.,Beijing 100094,China)
出处
《自动化仪表》
CAS
2022年第6期59-62,共4页
Process Automation Instrumentation
关键词
核电厂
事故后监视系统
F-SC1等级
系统设计
变量分类
Nuclear power plant
Post-accident monitoring system(PAMS)
F-SC1 class
System design
Variable classification
