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核安全级数字化仪控系统软件安全性分析研究
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  • 英文篇名:Study About Software Security Analysis for the Safety Digital I&C System of NPP
  • 作者:谷鹏飞 ; 刘子寅 ; 席望 ; 黄伟军
  • 英文作者:Gu Pengfei;Liu Ziyin;Xi Wang;Huang Weijun;China Nuclear Power Engineering Co., Ltd.;Harbin Engineering University;
  • 关键词:数字化技术 ; 仪控系统 ; 核安全 ; 验证和确认 ; 软件安全性分析
  • 英文关键词:digital technology;;I&C system;;safety class;;V&V;;software security analysis
  • 中文刊名:仪器仪表用户
  • 机构:中广核工程有限公司设计院;哈尔滨工程大学;
  • 出版日期:2019-05-20
  • 出版单位:仪器仪表用户
  • 年:2019
  • 期:06
  • 语种:中文;
  • 页:100-102
  • 页数:3
  • CN:12-1334/TH
  • ISSN:1671-1041
  • 分类号:TM623
摘要
随着数字化技术全面应用于核电站仪控系统,与过去的模拟技术相比,其控制更集中,信息处理更复杂,信息关联性更强。但是庞大且集中的仪控系统所引起的安全性分析工作日益引起人们的重视,尤其是核安全级数字化仪控系统,它能否正常工作直接关系着核电站的安全。本文以核安全级数字化仪控系统在核电站的工程实践为例,结合软件验证和确认(V&V)的相关法规标准,分析了核安全级数字化仪控系统软件安全性分析所面临的主要问题,并提出了软件安全性分析工作的主要内容,为后续核电站的相关实际工作提供技术参考。
        With the digital technology used in the I&C system, comparing with the past, I&C system is more centralized control,more complex information processing, more information relevance. However, security analysis which is triggered by large and concentrated I&C system has been paid more attention, especially in the safety digital I&C system. Regarded the safety digital I&C system in nuclear power plant(NPP) as an example, combined with the relevant laws and regulations standard about V&V, this paper analyzes the main problems about software safety analysis in the safety digital I&C system, and gives the main contents. As a result, it is also benefit to the practice as the technical references.
引文
[1]刘真,江国进,孙永滨.核电安全级仪控系统软件V&V活动及其方法研究[J].核科学与工程,2011,12(S2):45-50.
    [2]R.G.1.168-2004,Verification,Validation,Reviews and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.
    [3]软件安全性:NASA 8719.13B-2004[S].2004.
    [4]核电厂设计安全规定:HAF102-2004[S].2004.
    [5]核动力厂基于计算机的安全重要系统软件:HAD 102/16-2004[S].2004.
    [6]IEC 60880-2006,Nuclear Power Plants-Instrumentation and Control Systems Important to Safety-Software Aspect for Computer-based Systems Performing Category A Functions[S].2006.
    [7]IEEE 7-4.3.2-2010.IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations[S].2010.
    [8]IEEE 1012-2012,IEEE Standard for System and Software Verification and Validation[S].2012.

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