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核电厂数字化反应堆保护系统多样性设计研究

Research of diversity design of digital reactor protection system for nuclear power plant
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摘要 在应对数字化反应堆保护软件共因故障的有关问题时,当前国际上普通采取的设计措施为设计一套与保护系统数字化软件处理部分独立的多样式保护系统。为了探索其他可能的纵深防御及多样性设计技术,提出基于两套(假设已满足NUREG/CR6303多样性要求的)核安全级数字化仪控平台构建核电厂保护系统,该系统满足抵御保护系统软件共因故障的要求,具备纵深防御及多样性特征的反应堆保护系统。 Design of an individual diversity protection system independent to the software processing part of reactor protection system is widely internationally when coping with the related problems of software common cause failure for digital reactor protection system. In order to make a research of other possible D3 technology. An additional design scheme is proposed in this paper, that is construct a digital reactor protection system with D3character based on two different digital I&C platforms which are supposed to meet the diversity requirements of NUREG/CR 6303.
作者 田露 吴坤 刘宏春 向思宇 吴坤任 Tian Lu;Wu Kun;Liu Hongchun;Xiang Siyu;Wu Kunren(Qinshan Nuclear Power Co.,LTD.,Jiaxing 314300,China;Nuclear Power Institute of China,Chengdu 610213,China)
出处 《电子技术应用》 2022年第S01期13-18,共6页 Application of Electronic Technique
关键词 软件共因故障 多样性 反应堆保护 两套核安全级数字化平台 software common cause failure diversity reactor protection system two different digital I&C platforms
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  • 1周海祥.核电厂数字化反应堆保护系统结构可靠性研究[D].哈尔滨:哈尔滨工业大学,2006.
  • 2李明宗.美国OCONEE核能电厂安全仪控系统数位化更新经验[R].台湾:台湾电力公司,1999.
  • 3NRC. Digital Instrumentation and Control System in Nuclear Power Plants.[R].Washington,D.C. NATIONNAL ACADEMY, 1997.
  • 4George E. Apostolakis.Digital Instrumentation and Control Issues in Nuclear Reactor Safety[R].US Harvard University, 2004.
  • 5NRC. SAFETY EVALUATION BY TIlE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 366 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 38 AND DUKE ENERGY CAROLINAS, LLC AMENDMENT NO. 368 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 47 AMENDMENT NO. 367 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3. 2010.
  • 6Takaki Mishima. Construction and operation experience of digitalized Safety Systems of Japanese ABWR[R], 2009.
  • 7蒋祖跃.秦山核电厂反应堆保护系统及其相关设备数字化改造规划和实施策略[J].原子能科学技术,2010,44(1):65-69. 被引量:10
  • 8朱毅明.核电站数字化控制系统的应用和发展——2010年中国战略性新兴产业与仪器仪表发展论坛上的讲话[J].中国仪器仪表,2010(12):21-24. 被引量:3

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