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Development and Demonstration of Inferential Flow Characterization Techniques for Novel Advanced Reactors

机译:新型先进反应器推论流量表征技术的开发与论证

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摘要

Integral primary systems offer significant safety advantages by eliminating opportunities for large-break loss of coolant accidents. However, direct measurement of the primary system flow rate over long fuel cycles and reactor lifetimes can be challenging. A forced-circulation water-based flow loop is being constructed at the University of Tennessee to develop and validate inferential flow characterization methods that will be widely applicable to a variety of integral primary systems.
机译:整体式一次系统消除了冷却剂意外大面积损失的机会,因此具有显着的安全优势。但是,直接测量较长的燃料循环和反应堆寿命上的一次系统流量可能是一个挑战。田纳西大学正在建造一个强制循环的水流回路,以开发和验证推论性的流量表征方法,该方法将广泛适用于各种整体式主系统。

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  • 来源
    《Transactions of the American nuclear society》 |2015年第1期|467-470|共4页
  • 作者单位

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

    Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300, USA;

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