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首页> 外文期刊>Thermal engineering >Experimental Simulation of Hydrodynamics and Heat Transfer in Bubble and Slug Flow Regimes in a Heavy Liquid Metal
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Experimental Simulation of Hydrodynamics and Heat Transfer in Bubble and Slug Flow Regimes in a Heavy Liquid Metal

机译：重金属中气泡和团状流态的流体动力学和传热实验

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摘要

For the confirmation of the claimed design properties of a reactor plant with a heavy liquid-metal coolant, computational and theoretical studies should be performed in order to justify its safety. As one of the basic scenarios of an accident, the leakage of water into the liquid metal is considered in the case of steam generator tube decompression. The most important in the analysis of such a kind of accidents are questions concerning the motion and heat exchange of steam bubbles in the steam generator and the probability of blocking the flow area owing to freezing coolant, since the temperature of boiling feedwater in the steam generator can become lower than the melting point of lead. In this paper, we present main approaches and relationships used for the simulation of the motion of gas bubbles and heat transfer between bubbles and liquid metal flow. A brief description of the HYDRA-IBRAE/LM computational code that can be used to analyze emergency situations in a liquid metal-cooled reactor facility is also presented. It should be noted that the existing experimental data on the motion and heat transfer of gas bubbles in a heavy liquid metal are insufficient. For this reason, in order to verify the HYDRA-IBRAE/LM code models, experiments have been performed on the cooling of liquid lead by argon and on the motion of gas bubbles in the Rose’s alloy. In particular, a change in the temperature of the coolant over time has been studied, and the void fraction of gas at different flow rates of gas has been measured. A detailed description of the experiments and a comparison of the results of the calculations with the experimental data are presented. The analysis of uncertainties made it possible to reveal the main factors that exert the greatest effect on the results of calculations. The numerical analysis has shown that the models incorporated into the HYDRA-IBRAE/LM code allow one to describe to a sufficient degree of confidence the process of cooling liquid lead melt when argon bubbles pass through it, simulating the flow of water into the liquid metal in the course of steam generator tube rupture.
机译：为了确认使用重金属液体冷却剂的反应堆装置的要求保护的设计特性，应进行计算和理论研究以证明其安全性。作为事故的基本情况之一，在蒸汽发生器管减压的情况下，考虑了水泄漏到液态金属中。在此类事故的分析中，最重要的问题是关于蒸汽发生器中蒸汽气泡的运动和热交换，以及由于蒸汽发生器中沸腾的给水温度引起的，由于冷却剂冻结而阻塞流动区域的可能性的问题。会变得低于铅的熔点。在本文中，我们介绍了用于模拟气泡运动以及气泡与液态金属流之间的传热的主要方法和关系。还简要介绍了可用于分析液态金属冷却反应堆设施中紧急情况的HYDRA-IBRAE / LM计算代码。应当指出，有关重金属液体中气泡运动和传热的现有实验数据是不够的。因此，为了验证HYDRA-IBRAE / LM代码模型，已经进行了关于通过氩气冷却液态铅以及对Rose合金中气泡运动的实验。特别地，已经研究了冷却剂的温度随时间的变化，并且已经测量了在不同的气体流速下的气体的空隙率。给出了对实验的详细说明，并将计算结果与实验数据进行了比较。对不确定性的分析可以揭示对计算结果产生最大影响的主要因素。数值分析表明，HYDRA-IBRAE / LM代码中包含的模型可以使人们以足够的置信度描述氩气通过时冷却液态铅熔体的过程，从而模拟水向液态金属的流动在蒸汽发生器管破裂的过程中。

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  • 来源
    《Thermal engineering》 |2018年第8期|562-567|共6页
  • 作者

    E. V. Usov; P. D. Lobanov; A. E. Kutlimetov; I. G. Kudashov; V. I. Chukhno; S. I. Lezhnin; N. A. Pribaturin; O. N. Kashinsky; A. I. Svetonosov; N. A. Mosunova;

  • 作者单位

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Institute of Thermophysics, Russian Academy of Sciences, Siberian Branch;

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Novosibirsk Branch of the Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

    Institute of Thermophysics, Russian Academy of Sciences, Siberian Branch;

    Institute of Thermophysics, Russian Academy of Sciences, Siberian Branch;

    Institute for Problems of Safe Development of Nuclear Power Engineering, Russian Academy of Sciences;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    liquid metal; heat transfer; two-phase flow; gas bubble; closing relations; HYDRA-IBRAE/LM code; lead; Rose’s alloy; verification;

    机译：液态金属传热两相流气泡闭合关系HYDRA-IBRAE / LM代码铅罗斯合金验证;

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