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核电站数字化保护系统控制层通信协议的设计

Design of Control Layer Communication Protocolfor Nuclear Power Plant Digital Protection System
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摘要 核电站数字化保护系统中的控制层通信承担着重要的数据和信息传输任务,为控制单元提供现场数据和保护输出,是核电站数字化保护系统中的重要组成部分。现有的控制层通信协议无法满足核电站数字化保护系统确定性、可靠性、独立性和实时性的要求。采用基于状态、通信周期固定、通信链路冗余、只传输固定的数据集、帧长度和格式固定等方式,设计了控制层通信协议。根据核电标准要求,针对通信协议中可能存在的故障类型进行了分析,同时给出了错误检测方法和相应的处理措施,以满足核电站数字化保护系统确定性、可靠性、独立性和实时性的要求。该通信协议已经通过权威机构认证,所涉及的硬件产品已经通过核安全级设备的鉴定,后续可应用于军工、航天等高可靠性行业。 In the digital protection system of nuclear power plant, the control layer communication undertakes important data and information transmission tasks to provide field data and protection output for the control unit, is an important part of the digital protection system of nuclear power plant. The existing control layer communication protocols can not meet the requirements of determinism, reliability, independence and real-time of nuclear power plant digital protection system. The designed control layer communication protocol adopts state-based, fixed communication period, redundant communication links, transmission of only fixed data sets, and fixed frame length and format. According to the requirements of nuclear power standards, the possible types of faults in the communication protocol are analyzed, and the error detection methods and corresponding processing measures are also given to meet the requirements of determinism, reliability, independence and real-time of the digital protection system of nuclear power plants. The communication protocol has been certified by authoritative organizations, and the hardware products involved have been authenticated as nuclear safety grade equipment, which can be subsequently applied to military, aerospace and other high-reliability industries.
作者 周飞 ZHOU Fei(China Techenergy Co.,Ltd.,Beijing 100094,China)
出处 《自动化仪表》 CAS 2023年第12期85-90,共6页 Process Automation Instrumentation
关键词 核电站 数字化保护系统 控制层通信协议 基于状态的通信 冗余网络 安全性 可靠性 确定性 Nuclear power plant Digital protection system Control layer communication protocol State-based communication Redundant network Safety Reliability Determinism
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二级参考文献6

  • 1IEEE Std 7-4.3.2-2003,IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations[S].
  • 2IEEE Std 603-1998,IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations[S].
  • 3[EC 61500-2009,Data communication in systems performing category A functions October 2006[S].
  • 4NUKEG/CR-6082,Data Conmaunications August 1993[S].
  • 5Nuclear power plants - Instrumentation and control systems important to safety - Separation[S].
  • 6DI&C-ISG-04,Highly-Integrated control rooms-communications issues,March 2009[S].

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