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Design of the Instrumentation and Control for the ITER Tokamak Cooling System

机译:ITER托卡马克冷却系统的仪表和控制设计

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摘要

The design strategy for TCWS I&C system is similar to the strategy/guidelines of conventional nuclear power plants. Independence, communication pathways, sharing of sensors, qualification of hardware/software, risk goals, etc. are all important aspects considered in the design. Finally, while qualification standards provide similar guidance in both technologies (e.g., IEEE 323 and IEC 60780), the radiation profile and magnetic field environments are different.
机译:TCWS I&C系统的设计策略与常规核电站的策略/指南相似。独立性,通信路径,传感器共享,硬件/软件的鉴定,风险目标等都是设计中要考虑的重要方面。最后,尽管资格标准在两种技术(例如,IEEE 323和IEC 60780)中提供了类似的指导,但是辐射曲线和磁场环境却不同。

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  • 来源
    《Transactions of the American nuclear society》 |2013年第1期|451-454|共4页
  • 作者单位

    U.S. ITER Oak Ridge National Laboratory, Box 2008 Oak Ridge, TN 37831-6075, USA;

    U.S. ITER Oak Ridge National Laboratory, Box 2008 Oak Ridge, TN 37831-6075, USA;

    AREVA Federal Services, LLC Charlotte, NC, USA;

    AREVA Federal Services, LLC Charlotte, NC, USA;

    AREVA Federal Services, LLC Charlotte, NC, USA;

    AREVA Federal Services, LLC Charlotte, NC, USA;

    AREVA Federal Services, LLC Charlotte, NC, USA;

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  • 正文语种 eng
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