期刊文献+

先进逻辑系统平台的保护与监测系统的D3分析 被引量:2

Diversity and Defense-in-depth Analysis of the PMS Based on ALS Platform
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摘要 2013年美国核管会通过了对西屋公司开发的新一代基于现场可编程门阵列技术的1E级先进逻辑系统平台的认证。针对基于该平台所设计的保护与监测系统,依据NUREG/CR 6303的相关要求,进行了多样性和纵深防御要求分析,并按NUREG/CR 7007的方法计算了保护与监测系统的多样性量化值。分析结果表明,新设计的保护与监测系统方案基本满足美国核管会对系统多样性的定量要求,并得出可以不单独设置多样性驱动系统的初步结论。 In 2013,the new generation Class 1E ALS platform based on FPGA technology developed by Westinghouse Electric Company had been approved by US NRC. Aiming at the protection and monitoring system( PMS) designed based on this platform,in accordance with the requirements of NUREG/CR 6303,the analysis of diversity and defense-in-depth is conducted; and the quantitative value of diversity for PMS is calculated by using the method of NUREG/CR 7007. The results of analysis indicate that the newly designed PMS basically meets the diversity requirements of US NRC,and the preliminary conclusion of eliminating diversity actuation system is obtained.
作者 徐智
出处 《自动化仪表》 CAS 2016年第2期22-29,共8页 Process Automation Instrumentation
关键词 核电站 安全系统 数字化 多样性与纵深防御 核反应堆 保护与监测系统 安全评估 共模故障 仪控系统 紧急停堆 Nuclear power plant Safety system Digitization Diversity and defense-in-depth(D3) Nuclear reactor Protection and detection system Security assessment Common mode failure I&C system Emergency shut down
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参考文献11

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二级参考文献28

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共引文献17

同被引文献22

  • 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
  • 2US NRC.NUREG/CR-6303 method for performing diversity and defense-in-depth analyses of reactor protection systems[S], 1994.
  • 3US NRC.BTP7-19 guidance for evaluation of diversity and de- fense-in-depth in digital computer-based instrumentation and control system[S] ,2007.
  • 4US NRC.NUREG/CR-7007 diversity strategies for nuclear power plant instrumentation and control systems[S] ,2009.
  • 5NRC U S. Nuclear regulatory commission safety evaluation for topical report 6002-00301 "Advanced Logic System Topical Report"[R].Rock ville :NRC,2013.
  • 6Bill R,Royce B ,Deanna Z,et.al.Audit report for lifecycle phas- es one and two documentation validation related to protection and safety monitoring system and diverse actuation system for the ap1000 design certification amendment application[R].Rock Ville : NRC, 2010.
  • 7Bill R,Jack Y,Ken D,et al.Audit report for review of propri- etary technical,procedural,and process information related to the component interface module and diverse actuation systems for the westinghouse ap1000 design certification amendment ap- plication[R].Rock Ville:NRC,2010.
  • 8NRC.Wolf creek nuclear operating corporation-amendment to re- newed facility operating license[R].NRC,Washington DC,2009.
  • 9Diablo Canyon Power Plant. Supplement to license amendment request 11-07.Process protection system replacement [R].Avila Beach,CA,2013.
  • 10黄礼渊.研究堆周期保护装置堆上考验试验[J].核电子学与探测技术,2011,31(9):1029-1034. 被引量:2

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