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核电厂反应堆保护系统数字化升级关键要素探究

Research on Key Elements of Digital Upgrade of Reactor Protection System in Nuclear Power Plant
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摘要 国内早期建成的反应堆保护系统亟需开展数字化升级,以解决原系统设备老化、故障率高、备件停产、缺乏服务保障等问题,但是软件控制手段与模拟技术存在显著的差异,需要在设计环节重点考虑并妥善解决,才能确保改造后机组安全稳定运行。以某核电厂数字化升级改造实践为背景,重点研究了缺省值、网络安全、软件共因故障等问题,提出了一套设计解决方案,对于后续反应堆保护系统数字化升级项目工程应用具有借鉴意义。 The reactor protection system built early in China needs to be upgraded digitally to solve the problems of aging equipment,high failure rate,shutdown of spare parts and lack of service guarantee,etc.However,there are significant differences between software control means and simulation technology,which need to be considered and properly solved in the design process to ensure the safe and stable operation of the modified system.Based on the practice of digital upgrading of a nuclear power plant,the problems such as default value,network security,common cause failure of software,are emphatically studied,and a design solution was proposed,which has reference significance for the subsequent digital upgrading project of reactor protection system.
作者 何玉鹏 张谊 姜静 周岱 彭浩 He Yupeng;Zhang Yi;Jiang Jing;Zhou Dai;Peng Hao(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处 《仪器仪表用户》 2023年第11期41-44,共4页 Instrumentation
基金 国家重点研发计划项目(2022YFB3305200) 四川省重大科技专项项目(2022ZDZX0008)。
关键词 核电厂 反应堆保护系统 数字化改造 nuclear power plant reactor protection system digital upgrade
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  • 1蒋祖跃.秦山核电公司仪控综合改造(反应堆保护系统及其相关设备部分)可行性研究报告,2005.11-62.
  • 2CHAO Ping, XU Dongling. Detail stages 1-3 of the process engineering task description for the Reactor Protection System, Q1.E.GZY25.S.05SJ-0005, 2005. 1-23.
  • 3Tech. Reactor Protection System, Description of Overall Concept, Q1.E.GZY25.F.05SJ-0101, 2007.47-52.
  • 4Tech. TELEPERM XS - Verification and Validation Program, Q1.E.GZY25.F.05SJ-0106, 2006. 13-15.
  • 5国家核安全局.HAF102-2004核动力厂设计安全规定[S].北京:中国法制出版社,2004.
  • 6国家技术监督局.GB/T 5963-1995 反应堆保护系统的隔离准则[S].北京:中国标准出版社,1995.
  • 7IEC 60880-1986 Software for computer in the safety systems of nuclear power stations[S].Geneva:IEC,1986.
  • 8IEC 60880-2-2000 Software for computer in the safety systems of nuclear power stations part 2:Software aspects of defense against common cause failures,use of software tools of pre-developed software[S].Geneva:IEC,2000.
  • 9NUREG-0800 Rev.4 Section 7.0 Instrumentation and controls-overview of review process[S].Washington D.C.,U.S.:NRC,1997.
  • 10管运全,徐霞军,王琪,翟世民.田湾核电站安全仪控系统运行及维护经验[J].核电子学与探测技术,2013,33(3):345-348. 被引量:6

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