期刊文献+

反应堆保护系统通信故障分析和优化方案研究

Study of Communication Failure Analysis and Optimization Schemes for Reactor Protection Systems
在线阅读 下载PDF
导出
摘要 核电站反应堆保护系统采用通信的方式实现重要保护信号的传输。为提升传输可靠性,以反应堆保护系统通信设计方案为研究对象,针对通信路径中的单一通信板卡故障风险,提出基于和睦系统的核电站专设安全设施驱动功能通信链路的设计优化方案。从通信故障后果、系统可靠性数据、性能指标和硬件变更范围方面,对设计优化方案的效果和可行性进行理论分析,并搭建实物样机进行测试验证。理论分析和验证结果证明通信设计优化对于减少通信设备故障的影响具有实用效果,有利于保障核电站的安全和经济性。该研究为后续不同堆型核电机组的建设,以及在役核电机组的优化改造提供了重要参考。 The reactor protection system of nuclear power plant adopts communication to realize the transmission of important protection signals.To enhance transmission reliability,the reactor protection system communication design scheme is taken as the object of study,and the design optimization scheme of the communication link for the drive function of nuclear power plant engineered safety feature based on the FirmSys is proposed in view of the risk of failure of a single communication board in the communication path.The effect and feasibility of the design optimization scheme are theoretically analyzed in terms of the consequences of communication failures,system reliability data,performance indexes,and the scope of hardware changes,and physical prototypes are built for testing and verification.The theoretical analysis and validation results prove that communication design optimization has practical effects on reducing the effects of communication equipment failures,which is conducive to safeguarding the safety and economy of nuclear power plants.This study provides an important reference for the subsequent construction of nuclear power units of different reactor types,as well as the optimization and transformation of in-service nuclear power units.
作者 王潇 刘波 马志国 夏利民 吉一哲 吴桂生 WANG Xiao;LIU Bo;MA Zhiguo;XIA Limin;JI Yizhe;WU Guisheng(China Techenergy Co.,Ltd.,Beijing 100094,China)
出处 《自动化仪表》 2025年第9期45-50,共6页 Process Automation Instrumentation
关键词 核电站 通信链路 单一故障 误动作 表决逻辑 专设安全设施 Nuclear power plant Communication link Single fault False action Voting logic Engineered safety feature
  • 相关文献

参考文献5

二级参考文献14

  • 1国家核安全局HAF102,核动力厂设计安全规定[S].1991.
  • 2国家核安全局.HAD102,核动力厂设计总的安全原则[S].1989.
  • 3IEEE Std 7-4.3.2-2003,IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations[S].
  • 4IEEE Std 603-1998,IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations[S].
  • 5[EC 61500-2009,Data communication in systems performing category A functions October 2006[S].
  • 6NUKEG/CR-6082,Data Conmaunications August 1993[S].
  • 7Nuclear power plants - Instrumentation and control systems important to safety - Separation[S].
  • 8DI&C-ISG-04,Highly-Integrated control rooms-communications issues,March 2009[S].
  • 9刘宏春,王涛涛,王华金,周继翔,刘光明,许东方.岭澳二期核电站数字化反应堆保护系统[J].核动力工程,2008,29(1):1-4. 被引量:27
  • 10张冬冬,蒙海军.红沿河核电站安全级DCS控制系统设计[J].电力建设,2009,30(6):66-68. 被引量:19

共引文献40

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部