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Experimental investigation of the impulse gas injection into liquid and the use of experimental data for verification of the HYDRA-IBRAE/LM thermohydraulic code

机译:脉冲气体注入液体的实验研究以及使用实验数据验证HYDRA-IBRAE / LM热工代码

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摘要

Experiments with impulse gas injection into model coolants, such as water or the Rose alloy, performed at the Novosibirsk Branch of the Nuclear Safety Institute, Russian Academy of Sciences, are described. The test facility and the experimental conditions are presented in details. The dependence of coolant pressure on the injected gas flow and the time of injection was determined. The purpose of these experiments was to verify the physical models of thermohydraulic codes for calculation of the processes that could occur during the rupture of tubes of a steam generator with heavy liquid metal coolant or during fuel rod failure in water-cooled reactors. The experimental results were used for verification of the HYDRA-IBRAE/LM system thermohydraulic code developed at the Nuclear Safety Institute, Russian Academy of Sciences. The models of gas bubble transportation in a vertical channel that are used in the code are described in detail. A two-phase flow pattern diagram and correlations for prediction of friction of bubbles and slugs as they float up in a vertical channel and of two-phase flow friction factor are presented. Based on the results of simulation of these experiments using the HYDRA-IBRAE/LM code, the arithmetic mean error in predicted pressures was calculated, and the predictions were analyzed considering the uncertainty in the input data, geometry of the test facility, and the error of the empirical correlation. The analysis revealed major factors having a considerable effect on the predictions. The recommendations are given on updating of the experimental results and improvement of the models used in the thermohydraulic code.
机译:描述了在俄罗斯科学院核安全研究所新西伯利亚分校进行的将脉冲气体注入模型冷却剂(例如水或玫瑰合金)中的实验。详细介绍了测试设备和实验条件。确定了冷却剂压力对喷射气体流量和喷射时间的依赖性。这些实验的目的是验证热工液压代码的物理模型,以计算使用重液态金属冷却剂的蒸汽发生器的管道破裂期间或在水冷堆中燃料棒故障期间可能发生的过程。实验结果用于验证由俄罗斯科学院核安全研究所开发的HYDRA-IBRAE / LM系统热工代码。详细介绍了代码中使用的垂直通道中的气泡传输模型。给出了两相流模式图和相关性,用于预测气泡和团块在垂直通道中漂浮时的摩擦以及两相流的摩擦因数。根据使用HYDRA-IBRAE / LM代码进行的这些实验的模拟结果,计算了预测压力中的算术平均误差,并考虑了输入数据,测试设备的几何形状和误差中的不确定性对预测进行了分析经验相关性分析揭示了对预测有相当大影响的主要因素。给出了有关更新实验结果和改进热工液压代码中使用的模型的建议。

著录项

  • 来源
    《Thermal engineering》 |2017年第10期|770-776|共7页
  • 作者单位

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

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

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

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

    Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN), Moscow, Russian Federation;

    Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN), Moscow, Russian Federation;

    Novosibirsk National Research State University, Novosibirsk, Russian Federation;

    Novosibirsk National Research State University, Novosibirsk, Russian Federation;

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

    calculation code; heavy liquid metal coolant; HYDRA-IBRAE/LM; Rose’s alloy; two-phase processes;

    机译:计算代码;重金属液态冷却剂;HYDRA-IBRAE / LM;玫瑰的合金;两阶段过程;

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