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NONHOMOGENEOUS-NONEQUIUBRIUM TWO-PHASE-FLOW MODEL FOR NUCLEAR REACTOR SINGLE-CHANNEL STABILITY ANALYSIS

机译:核反应器单通道稳定性分析的非均相非二相流模型

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摘要

The effects of two-phase-flow modeling on nuclear reactor single-channel stability analysis are investigated with four two-phase-flow models, namely, the homogeneous-equilibrium model, the homogeneous-nonequilibrium model, the nonhomogeneous-equilibrium model, and the nonhomogeneous-nonequilibrium model. The models are applied to hot-channel analyses of a proposed typical supercritical-water-cooled-reactor (SCWR) design. The neutral stability boundaries derived by using the four mod-els are compared and plotted on the traditional subcool-ing number versus phase change number plane. To ensure proper development of the models, they are benchmarked to the experimental data. It is found that the homogeneous models predict more conservative stability boundaries than the nonhomogeneous models and that the differences of the stability boundaries predicted by all four two-phase-flow models are reduced under higher-pressure conditions.
机译:利用均相平衡模型,均相非平衡模型,非均质平衡模型和均相平衡模型这四个模型,研究了两相流模型对核反应堆单通道稳定性分析的影响。非均匀非平衡模型。该模型可用于拟议的典型超临界水冷反应器(SCWR)设计的热通道分析。比较了使用四个模型得出的中性稳定性边界,并在传统的过冷数与相变数平面上进行了绘制。为了确保模型的正确开发,将它们作为实验数据的基准。发现均质模型比非均质模型预测更保守的稳定边界,并且在高压条件下,所有四个两相流模型预测的稳定边界的差异都减小了。

著录项

  • 来源
    《Nuclear Technology》 |2012年第1期|p.78-88|共11页
  • 作者单位

    EXQUISITUS, Centre for E-City, School of Electrical and Electronics Engineering,Nanyang Technological University, Singapore;

    Nanyang Technological University, School of Mechanical and Aerospace Engineering,Division of Thermal and Fluids Engineering, Singapore;

    EXQUISITUS, Centre for E-City, School of Electrical and Electronics Engineering,Nanyang Technological University, Singapore;

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

    reactor stability; two-phase-flow models; stability; map;

    机译:反应堆稳定性两相流模型;稳定性;地图;

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