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IEC 60880和IEEE 1012在核安全审评中的适用性分析 被引量:1

Applicability Analysis of IEC 60880 and IEEE 1012 in Nuclear Safety Reviewing
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摘要 IEC 60880和IEEE 1012是核电厂数字化仪表和控制(I&C)系统软件验证与确认(V&V)活动的主要参考标准,两者在软件V&V的具体要求方面不尽相同.由于在实际开发过程中,大多数国内核安全级软件开发单位通常同时执行IEC 60880和IEEE 1012,所以在核安全审评时,审评者如何结合具体核安全要求来掌握上述两项标准的适用性是一个值得研究的问题.论文通过系统对比的方法,对IEC 60880和IEEE 1012在V&V流程、独立性、软件安全、工具评估等方面的异同点进行了逐一分析,并结合相关支撑性标准体系以及核电厂安全要求,给出了两者在核安全软件审评中的适用性分析及应用技术见解,对于研究核安全软件审评方法具有一定的指导意义. As the main reference standards of verification and validation(V&V)activities for the digital instrumentation and control(I&C)system in nuclear power plants,IEC 60880 and IEEE 1012 are not completely identical in specific requirements of software V&V.In practice,most of domestic nuclear safety software suppliers normally employ both IEC 60880 and IEEE 1012 in development phase,so it is a worthful issue for the regulators that how to manage the applicability of these two standards with nuclear safety requirments in reviewing process.By means of systemic analysis,the similarities and differences in each part of IEC 60880 and IEEE 1012 in V&V process,independence,software safety,tools evalutaion etc.are compared,and applicability analysis and technical opinions for nuclear safety reviewing combined with supporting standards system and safety requirements of nuclear power plant are presented as well,which are instuctive for the researching of nuclear safety software reviewing methodology.
作者 黄伟杰 尹宝娟 毛从吉 张宓 HUANG Weijie;YIN Baojuan;Mao Congji;ZHANG Mi(Nuclear and Radiation Safety Center,Beijing 100082,China)
出处 《上海交通大学学报》 EI CAS CSCD 北大核心 2018年第S1期117-121,共5页 Journal of Shanghai Jiaotong University
关键词 验证与确认 数字化仪表和控制 标准体系 技术见解 verification and validation digital instrumentation and control standard system technical opinion
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  • 1U. S. Nuclear Regulatory Commission. NUREG/CR - 6992 Instrumentation and Controls in Nuclear Power Plants: Emerging Technologies Updates[ S]. Washing- ton DC ,2009. 被引量:1
  • 2U. S. Nuclear Regulatory Commission. NUREG/CR - 7006 Review Guidelines for Field - Programmable Gate Arrays in Nuclear Power Plant Safety Systems [ S]. Washington DC,2010. 被引量:1
  • 3International Electrotechn. cal Commission. CEI/IEC 60880- 2006 Nuclear power plants Instrumentation and control systems important to safety Software as- pects for computer - based systems performing catego- ry A functions [ S ]. Switzerland,2006. 被引量:1
  • 4EPRI. Technical Report 1019181 Guidelines on the Use of Field Programmable Gate Arrays (FPGAs) in Nuclear Power Plant I&C Systems [ S ]. Palo Alto, CA,2011. 被引量:1
  • 5International Electrotechnial Commissirn. CEI/IEC 62566- 2012 Nuclear power plants Instrumentation and control important to safety Development of HDL - programmed integrated circuits for systems performing category A functions [ S ]. Switzerland, 2012. 被引量:1
  • 6The Institute of Electrical and Electronics Engineers, Inc. IEEE std 1012 -2004 IEEE Standard for Software Verification and Validation [ S]. New York,2004. 被引量:1
  • 7The Institute of Electrical and Electronics Engineers,Inc. IEEE std. 1012 -2004 IEEE Standard for Soft- ware Verification and Validation [ S ]. New York, 2004. 被引量:1
  • 8The Institute of Electrical and Electronics Engineers, Ine. IEEE std. 1012 - 1986 IEEE Standard for Soft- ware Verification and Validation Plans [ S ]. New York, 1986. 被引量:1
  • 9The Institute of Electrical and Electronics Engineers, Inc. IEEE std. 1059 - 1993 IEEE Guide for Software Verification and Validation Plans [ S ]. New York, 1993. 被引量:1
  • 10The Institute of Electrical and Electronics Engineers, Inc. IEEE std. 1012 - 1998 IEEE Standard for Soft- ware Verification and Vahdation [ S ]. New York, 1998. 被引量:1

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