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福清核电厂5^(#)、6^(#)机组反应堆保护系统的设计 被引量:1

Design of Reactor Protection System for Units 5^(#)and 6^(#)of Fuqing Nuclear Power Plant
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摘要 反应堆保护系统是核电厂应对预期运行事件或设计基准事故而设置的重要安全级仪控系统。为满足“华龙一号”三代核电高安全性目标的设计要求,需要对反应堆保护系统的功能性能进行提升。以“华龙一号”示范工程福清核电厂5#、6#机组为研究对象,通过充分考虑保护系统设计准则要求并基于事故分析结论,提出了更具高可靠性和全面保护功能特征的反应堆保护系统设计方案。详细介绍了系统自动保护功能的设计、系统结构设计以及系统健康管理等内容,并对系统拒动率进行了定量分析。分析结果表明,系统总体拒动率不高于5.0×10^(-7)/指令,达到了国际主流三代核电的可靠性水平。该研究成果可为后续核电厂的反应堆保护系统设计或优化提供借鉴。 The reactor protection system is the important safety level instrumentation and control system for nuclear power plants in response to anticipated operational events or design basis accidents.To meet the design requirements of the“HPR1000”Generation III nuclear power with high safety objectives,the functional performance of the reactor protection system needs to be improved.Taking units 5#and 6#of the“HPR1000”demonstration project Fuqing Nuclear Power Plant as the target,the design of the reactor protection system with high reliability and comprehensive protection features is proposed by considering the requirements of the protection system design guidelines,and based on the conclusions of the accident analysis.The design of the automatic protection function,system structure design and system health management are introduced in detail,and the system rejection rate is analyzed quantitatively.The analysis results show that the overall rejection rate of the system is not higher than 5.0×10^(-7)/command,which reaches the reliability level of international mainstream Generation III nuclear power.The research results can provide reference for the design or optimization of reactor protection systems in subsequent nuclear power plants.
作者 刘宏春 冯威 李谢晋 贺理 陈鹏 王淼 丁书华 LIU Hongchun;FENG Wei;LI Xiejin;HE Li;CHEN Peng;WANG Miao;DING Shuhua(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
出处 《自动化仪表》 CAS 2023年第6期36-41,47,共7页 Process Automation Instrumentation
关键词 核电厂 华龙一号 安全级分布式控制系统 反应堆保护系统 共因故障 可靠性 定期试验 Nuclear power plant HPR1000 Safety level distributed control system(DCS) Reactor protection system Common cause failure Reliability Periodic test
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