期刊文献+

基于ALS平台的PMS数据通信设计分析 被引量:1

Analysis of PMS Data Communication Design Based on the ALS Platform
下载PDF
导出
摘要 采用基于软件系统的平台开发保护与监测系统时必须应对软件的固有共模故障问题,其安全认证是昂贵且复杂的工作。先进逻辑系统是西屋公司开发并通过NRC认证的新一代基于FPGA技术的1E级平台。为了能够应用该先进平台来开发保护与监测系统并降低取证的难度,基于该平台的特性、其在2个核电厂保护系统部分功能替换工程的实践以及核电厂保护与监测系统的典型功能需求,设计了一种基于ALS平台的保护与监测系统新的总体架构,并分析了该设计与DI&C-ISG-04要求的一致性。分析表明该设计满足安全系统数据通信的独立性和隔离要求,可应用于实际工程。 The software common mode failure is a critical issue to be addressed for the PMS developed with software based platform,such as Common Q or TXS. The licensing of the system is very expensive and hard usually. FPGA technology based ALS platform was designed by WEC and has been approved by NRC as the next generation 1E class platform for protection and monitoring system development for nuclear power plants. To facilitate the advantage of the most advanced platform for the PMS development and to relax the hard licensing jobs,based on the features of the platform and typical PMS function requirements,a new overall architecture with ALS for PMS is designed and the consistency with DI&C-ISG-04 is analyzed. The evaluation indicates the design meets the data communication independence and isolation requirements and can be referenced for engineering project.
作者 徐智 雷晴
出处 《自动化与仪表》 2015年第8期9-16,26,共9页 Automation & Instrumentation
关键词 先进逻辑系统 保护与监测系统 独立性 隔离 现场可编程逻辑阵列 数据通信 advanced logic system best regards(Al_S) protection and safety monitoring system(PMS) independence isolation field programmable gate array(FPGA) data communication
  • 相关文献

参考文献12

二级参考文献30

  • 1晁平,郑明光.田湾核电站数字化安全级仪控系统结构与性能研究[J].核电工程与技术,2003,16(4):27-32. 被引量:4
  • 2国家核安全局.HAFl02,核电厂设计安全规定[s].北京:中国法制出版社,2004. 被引量:1
  • 3国家核安全局.HADl02/10,核电厂保护系统及有关设施[s].北京:中国法制出版社,1988. 被引量:1
  • 4国家核安全局.HADl02/16,核动力厂基于计算机的安全重要系统软件[s].北京:中国法制出版社,2004. 被引量:1
  • 5IEEE Std. 1012, IEEE Standard for Software Verifica- tion and Validation [ S]. 2008. 被引量:1
  • 6IEEE Std. 323, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations [s]. 2o03. 被引量:1
  • 7IAEA technical report series No. 384, verification and validation of software related to nuclear power plant in- strumentation and control[S]. 1999. 被引量:1
  • 8IEEE Std. 7 - 4. 3.2, IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations[ S]. 2010. 被引量:1
  • 9U. S. Nuclear Regulatory Commission, DI&C -ISG -04. Highly Integrated Control Rooms Digital Com- munication Systems[ S]. 2009. 被引量:1
  • 10MHI, MUAP - 07005 - NP ( R7 ), Safety System Digital Platform MELTAC [ R ]. 2011. 被引量:1

共引文献21

同被引文献10

  • 1徐智,雷晴,陈冬雷.CIM和DAS多样性的定量分析[J].自动化仪表,2014,35(S01):73-76. 被引量:5
  • 2林诚格,郁祖盛.非能动安全先进压水堆核电技术[M].北京:原子能出版社,2008:150-176. 被引量:13
  • 3NRC U S. Nuclear Regulatory Commission Safety Evaluation for Topical Report 6002 - 00301 "Advanced Logic System Topical Report" [ R]. Rock ville:NRC. 2013. 被引量:1
  • 4NRC US. NUREG/CR - 6303 Method for performing diversity and defense - in - depth analyses of reactor protection systems [S]. 1994. 被引量:1
  • 5NRC US. NUREG/CR -7007 Diversity strategies for nuclear power plant instrumentation and control systems[S]. 2009. 被引量:1
  • 6NRC. Wolf creek nuclear operating corporation - amendment to renewed facility operating license [ R ]. NRC, Washington DC. 2009. 被引量:1
  • 7Diablo Canyon Power Plant. Supplement to license amendment request 11 - 07. process protection system replacement [ R ]. Avila Beach, CA ,2013. 被引量:1
  • 8Westinghouse L L C. Westinghouse AP1000 design control document [ R ]. Pittsburgh: Westinghouse Electric Company LLC ,2012. 被引量:1
  • 9徐智,雷晴.新型逻辑系统平台的保护与监测系统数据通信设计[J].核电子学与探测技术,2015,35(5):462-467. 被引量:3
  • 10徐智,丁丁,张瑜.基于NUREG/CR-7007的DAS优化设计[J].原子能科学技术,2016,50(1):156-163. 被引量:4

引证文献1

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