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首页> 外文期刊>International Journal of Heat and Mass Transfer >Modeling and analysis of supercritical flow instability in parallel channels
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Modeling and analysis of supercritical flow instability in parallel channels

机译：平行通道中超临界流动不稳定性的建模与分析

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摘要

With a view to better utilizing and further expanding the experimental results recently obtained on supercritical flow instability, an in-house code has been developed applying time-domain approach. Different ways of geometrical modeling of the test section in the experiments are studied. Comparison between the numerical and experimental results shows that the numerical code is capable to predict well the stability boundaries. Based on the validated code, the geometrical simplification is further discussed and a relatively simple as well as common geometrical configuration is proposed. Discussions also indicate that the entrance and riser sections cannot be eliminated with respect to numerical modeling of flow stability. Effects of inlet temperature and total mass flow rate are numerically analyzed. Results show that the inlet temperature has a non-monotonic effect on the threshold power, while the threshold power is roughly proportional to the total mass flow rate no matter the system is symmetrical or not. Moreover, the results indicate that it would be more difficult to perform flow instability experiments at higher inlet temperature or total mass flow rate.
机译：为了更好地利用和进一步扩展最近获得的关于超临界流不稳定性的实验结果，已开发出一种使用时域方法的内部代码。研究了实验中测试部分的几何建模的不同方式。数值和实验结果的比较表明，该数值代码能够很好地预测稳定性边界。基于验证码，进一步讨论了几何简化，并提出了一种相对简单以及常见的几何构造。讨论还表明，就流动稳定性的数值模拟而言，无法消除入口和立管部分。数值分析了入口温度和总质量流量的影响。结果表明，入口温度对阈值功率具有非单调影响，而无论系统是否对称，阈值功率都与总质量流量大致成比例。此外，结果表明，在较高的入口温度或总质量流量下进行流动不稳定性实验将更加困难。

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  • 来源
  • 作者

    Ting Xiong; Xiao Yan; Shanfang Huang; Junchong Yu; Yanping Huang;

  • 作者单位

    CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China,Department of Engineering Physics, Tsinghua University, Beijing 100084, China;

    CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China;

    Department of Engineering Physics, Tsinghua University, Beijing 100084, China;

    CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China,Department of Engineering Physics, Tsinghua University, Beijing 100084, China;

    CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China;

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

    flow instability; modeling; supercritical; parallel channels; numerical;

    机译：流量不稳定;造型;超临界并行通道;数值的;

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