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Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

机译:利用IIST设施的SBLOCA实验评估TRACE CCFL模型

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摘要

In this paper, the TRACE model for IIST facility is developed and verified with the Small Break loss of coolant accident (SBLOCA) experiment of IIST (Institute of Nuclear Energy Research Integral System Test) facility. By using the Wallis and Kutateladze correlations of countercurrent flow limitation (CCFL) model, the TRACE analyses results, such as break flow rate, primary pressure, and the temperature of cold-leg and hot-leg, are consistent with the IIST data. The results show the Kutateladze correlation of CCFL model can well predict the SBLOCA behavior and present good agreement with IIST experiment data in this paper. Besides, the sensitivity study results of Kutateladze correlation in CCFL model are verified and compared with the IIST data.
机译:本文通过IIST(核能研究集成系统测试研究所)设施的冷却液小断裂损失事故(SBLOCA)实验,开发并验证了IIST设施的TRACE模型。通过使用Wallis和Kutateladze的逆流限流(CCFL)模型的相关性,TRACE分析结果(如中断流量,一次压力以及冷腿和热腿的温度)与IIST数据一致。结果表明,CCFL模型的Kutateladze相关性可以很好地预测SBLOCA行为,并且与IIST实验数据具有良好的一致性。此外,验证了CCFL模型中Kutateladze相关性的敏感性研究结果,并将其与IIST数据进行了比较。

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  • 来源
    《Science and technology of nuclear installation》 |2012年第1期|p.731616.1-731616.8|共8页
  • 作者单位

    Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Road,Hsinchu 30013, Taiwan;

    Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C., No. 1000, Wenhua Road, Jiaan Village, Longtan Township,Taoyuan 32546, Taiwan;

    Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C., No. 1000, Wenhua Road, Jiaan Village, Longtan Township,Taoyuan 32546, Taiwan;

    Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Road,Hsinchu 30013, Taiwan;

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