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Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR

机译:隔板对BWR型压力管子通道内两相湍流混合速率影响的实验研究

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摘要

Turbulent mixing rate between adjacent subchannels in a two-phase flow has been known to be strongly dependent on the flow pattern. The most important aspect of turbulent motion is that the velocity and pressure at a fixed point do not remain constant with time even in steady state but go through very irregular high frequency fluctuations. These fluctuations influence the diffusion of scalar and vector quantities. The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type, heavy water moderated and boiling light water cooled natural circulation based reactor. The fuel bundle of AHWR contains 54 fuel rods set in three concentric rings of 12, 18 and 24 fuel rods. This fuel bundle is divided into number of imaginary interacting flow channel called subchannels. Alteration from single phase to two phase flow situation occurs in reactor rod bundle with raise in power. The two phase flow regimes like bubbly, slug-churn, and annular flow are generally encountered in reactor rod bundle. Prediction of thermal margin of the reactor has necessitated the investigation of turbulent mixing rate of coolant between these subchannels under these flow regimes. Thus, it is fundamental to estimate the effect of spacer grids on turbulent mixing between subchannels of AHWR rod bundle.
机译:已知两相流中相邻子通道之间的湍流混合速率强烈取决于流型。湍流运动的最重要方面是,即使在稳态下,固定点的速度和压力也不会随时间保持恒定,而是会经历非常不规则的高频波动。这些波动影响标量和矢量量的扩散。先进重水反应堆(AHWR)是一种立式压力管式,重水调节和沸腾轻水冷却的自然循环反应堆。 AHWR的燃料束包含54个燃料棒,分别位于12个,18个和24个燃料棒的三个同心环中。该燃料束被分成称为子通道的假想相互作用的流动通道的数量。随着功率的增加,反应堆棒束中发生从单相到两相流动的变化。在反应堆棒束中通常会遇到两相流态,如气泡状,团状搅动和环形流。为了预测反应堆的热裕度,必须研究在这些流动状态下这些子通道之间的冷却剂湍流混合速率。因此,估算间隔格架对AHWR棒束子通道之间的湍流混合的影响至关重要。

著录项

  • 来源
    《Kerntechnik》 |2017年第5期|535-544|共10页
  • 作者单位

    Natl Inst Technol, Mech Engn Dept, Raipur 492010, Chhattisgarh, India;

    Natl Inst Technol, Mech Engn Dept, Raipur 492010, Chhattisgarh, India;

    Bhabha Atom Res Ctr, Reactor Design & Dev Grp, Hall 7, Bombay 400085, Maharashtra, India;

  • 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

  • 入库时间 2022-08-18 00:39:41

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