期刊文献+

基于FirmSys平台的核电厂反应堆保护系统设计 被引量:8

Design of Nuclear Power Plant Reactor Protection System Based on FirmSys Platform
下载PDF
导出
摘要 反应堆保护系统用于监测与反应堆安全有关的物理和过程测量参数,确保在发生设计基准事故时自动触发紧急停堆和/或专设安全设施,从而保护反应堆中燃料包壳、一回路压力边界和安全壳的完整性,限制放射性物质向公众环境的释放。基于FirmSys平台,提出了应用于田湾5^(#)、6^(#)机组核电厂反应堆保护系统设计方案。详细介绍了系统结构、接口、多样性以及故障检测设计,并对保护系统设计方案与标准的符合性进行分析。分析结果表明,该系统设计方案满足单一故障、独立性、多样性、保护动作自动触发等安全设计准则,同时兼顾了电厂运行经济性,可为后续核电厂保护系统设计提供指导和借鉴。 The reactor protection system for monitoring physical measurement and process parameters related to the reactor safety ensures that emergency shut down and/or set up safety facilities are automatically triggered when the design basis accident occurs to protect the reactor fuel cladding,the primary circuit in the pressure boundary and the integrity of the containment,limiting the release of radioactive material to the public environment.Based on FirmSys platform,the design scheme of reactor protection system applied to Tianwan 5^(#)and 6^(#)NPP is proposed.The system structure,interface,diversity and fault detection design are introduced in detail,and the conformance between the protection system design scheme and the standard is analyzed.The analysis results show that the design scheme of the system meets the safety design criteria of single fault,independence,diversity and automatic triggering of protection action while taking the operation economy of the power plant into account,which can provide guidance and reference for the design of the protection system of the nuclear power plant in the future.
作者 罗炜 王银丽 陈学坤 陈智 金远 杜枢 杨静瑞 吴启涛 侯丽强 LUO Wei;WANG Yinli;CHEN Xuekun;CHEN Zhi;JIN Yuan;DU Shu;YANG Jingrui;WU Qitao;HOU Liqiang(National Key Laboratory of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu 610041,China)
出处 《自动化仪表》 CAS 2021年第S01期65-69,共5页 Process Automation Instrumentation
关键词 反应堆保护系统 FirmSys 多样性 单一故障 独立性 自检 定期试验 符合性 Reactor protection system FirmSys Diversity Single fault Independence Self-check Periodic test Conformity
  • 相关文献

参考文献2

二级参考文献12

  • 1国家核安全局.HAD102-10核动力厂设计总的安全原则[S].北京:中国法制出版社,1989.
  • 2IAEA. NS-G-1.3 Instrumentation and control systems important to safety in nuclear power plants [ S ]. VIENNA ,2002.
  • 3International Electrotechnical Commission. IEC Std. 61513 Nuclear power plants-instrumentation and control for systems important to safety-general requirements for systems [ S ]. Switzerland,2001.
  • 4International Electrotechnical Commission. IEC Std. 62340 Nuclear power plants-instnnnentation and control systems important to safety- requirements for coping with common cause failure ( CCF ) [ S ]. Switzerland ,2007.
  • 5国防科学技术工业委员会.EJ-T1058.2核电厂安全系统计算机软件.第2部分:预防软件导致的共因故障、软件工具和预开发软件的使用[s].北京:核工业标准化所,2005.
  • 6US NRC. DI&C-ISG-02 Interim staff guidance on diversity and defense-in-depth issues [ S]. 2007.
  • 7US NRC. BTP7-19 Guidance for evaluation of diversity and defense- in-depth in digital computer-based instrumentation and control systems [ S ]. 2007.
  • 8US NRC. NUREG/CR-6303 Method for performing diversity and defense-in-depth analyses of reaetor protection systems[ S]. 1994.
  • 9Institute of Electrical and Electronics Engineers. IEEE Std. 379 Standard application of the single-Failure criterion to nuclear power generating station safety systems[ S ]. New York ,2000.
  • 10Institute of Electrical and Electronics Engineers. IEEE Std. 384 IEEE standard criteria for independence of class 1E equipment and circuits [ S ]. New York,2008.

共引文献34

同被引文献47

引证文献8

二级引证文献2

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