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Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17n and SHRT-45R

机译:EBR-II关机排热测试SHRT-17n和SHRT-45R的热工液压分析

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摘要

As one of the six Generation-IV reactors, SFR (sodium-cooled fast reactor) is attracting more and more attention in recent years. To evaluate the SFR safety characteristics, the Shutdown Heat Removal Tests (SHRT) conducted by Argonne National Laboratory (ANL) were performed in Experimental Breeder Reactor-II (EBR-II) to verify inhere safety characteristics. To find the inaccuracies in the exist models and improve the simulating level for SFR, SHRT-17 and SHRT-45R have been chosen as the benchmar
机译:作为六个IV型反应堆之一,SFR(钠冷快堆)近年来受到越来越多的关注。为了评估SFR安全特性,由阿贡国家实验室(ANL)进行的关机排热测试(SHRT)在实验型增殖反应堆II(EBR-II)中进行,以验证此处的安全特性。为了找到现有模型中的误差并提高SFR的仿真水平,选择了SHRT-17和SHRT-45R作为基准。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2015年第11期|682-693|共12页
  • 作者单位

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China.;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    THACS; Loss-of-flow; EBR-II SHRT; Sodium cooled fast reactor; VV;

    机译:THACS;流量损失;EBR-II SHRT;钠冷快堆;V&V;

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