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首页> 外文期刊>Thermal engineering >System of closing relations of a two-fluid model for the HYDRA-IBRAE/LM/V1 code for calculation of sodium boiling in channels of power equipment
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System of closing relations of a two-fluid model for the HYDRA-IBRAE/LM/V1 code for calculation of sodium boiling in channels of power equipment

机译：HYDRA-IBRAE / LM / V1代码的双流体模型闭合关系系统，用于计算动力设备通道中的钠沸腾

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摘要

The system of equations from a two-fluid model is widely used in modeling thermohydraulic processes during accidents in nuclear reactors. The model includes conservation equations governing the balance of mass, momentum, and energy in each phase of the coolant. The features of heat and mass transfer, as well as of mechanical interaction between phases or with the channel wall, are described by a system of closing relations. Properly verified foreign and Russian codes with a comprehensive system of closing relations are available to predict processes in water coolant. As to the sodium coolant, only a few open publications on this subject are known. A complete system of closing relations used in the HYDRA-IBRAE/LM/V1 thermohydraulic code for calculation of sodium boiling in channels of power equipment is presented. The selection of these relations is corroborated on the basis of results of analysis of available publications with an account taken of the processes occurring in liquid sodium. A comparison with approaches outlined in foreign publications is presented. Particular attention has been given to the calculation of the sodium two-phase flow boiling. The flow regime map and a procedure for the calculation of interfacial friction and heat transfer in a sodium flow with account taken of high conductivity of sodium are described in sufficient detail. Correlations are presented for calculation of heat transfer for a single-phase sodium flow, sodium flow boiling, and sodium flow boiling crisis. A method is proposed for prediction of flow boiling crisis initiation.
机译：来自双流体模型的方程组被广泛用于对核反应堆事故中的热工过程进行建模。该模型包括用于控制冷却剂各相中质量，动量和能量平衡的守恒方程。传热和传质的特征，以及相之间或与通道壁之间的机械相互作用的特征，由封闭关系系统来描述。可以使用经过全面验证的紧密联系系统正确验证的外国和俄罗斯法规来预测冷却液的过程。关于钠冷却剂，关于该主题的公开出版物很少。提出了一种用于HYDRA-IBRAE / LM / V1热工液压代码中用于计算动力设备通道中钠沸腾的闭合关系的完整系统。根据对现有出版物的分析结果，并考虑到液态钠中发生的过程，可以确定这些关系的选择。介绍了与国外出版物中概述的方法的比较。特别注意钠两相流动沸腾的计算。充分详细地描述了考虑到钠的高电导率的流态图和计算钠流中界面摩擦和传热的程序。提出了用于计算单相钠流量，钠流量沸腾和钠流量沸腾危机的传热的相关性。提出了一种预测沸腾危机爆发的方法。

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  • 来源
    《Thermal engineering》 |2017年第7期|504-510|共7页
  • 作者

    Usov E. V.; Butov Anton A.; Dugarov G. A.; Kudasov I. G.; Lezhnin Sergey I.; Mosunova Nastasya A.; Pribaturin Nikolay A.;

  • 作者单位

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

    Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences, Novosibirsk Branch (NF IBRAE RAN), Novosibirsk, Russian Federation;

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  • 正文语种 eng
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  • 关键词

    closing relations; HYDRA-IBRAE/LM code; sodium; two-phase flow;

    机译：亲密关系;HYDRA-IBRAE / LM代码;钠;两相流;

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