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Two-phase flow-induced vibrations in a heated tube bundle.

机译:加热的管束中两相流动引起的振动。

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摘要

The U-bend region of nuclear steam generators tube bundles have suffered from two-phase cross flow induced vibrations. Tubes in this region have experienced high amplitude vibrations leading to catastrophic failures. Turbulent buffeting and fluidelastic instability have been identified as the main causes. Previous investigations have focused on flow regime and two-phase flow damping ratio. However, tube bundles in steam generators have vapour generated on the surface of the tubes, which might affect the flow regime, void fraction distribution, turbulence levels and tube-flow interaction, all of which have the potential to change the tube vibration response.; A cantilevered tube bundle made of electric cartridge heaters was built and tested in a Freon-11 flow loop. Tubes were arranged in a parallel triangular configuration with pitch to diameter ratio of 1.48. The bundle was exposed to two-phase cross flows consisting of different combinations of void from two sources, void generated upstream of the bundle and void generated at the surface of the tubes. Tube tip vibration response was measured optically and void fraction was measured by a gamma densitometry technique.; It was found that the ratio of tube vibration amplitude in the transverse direction was reduced by a factor of 8 for void fraction generated at the surface of the tubes only, when compared to the response observed under the upstream only void generation case. The main explanation for this effect is a reduction in the correlation length of the turbulent buffeting forcing function. Theoretical calculations of the tube vibration response due to turbulent buffeting under the same experimental conditions predicted a similar reduction in tube amplitude.; The void fraction for the fluidelastic instability threshold in the presence of tube bundle void fraction generation was higher than that for the upstream void fraction generation case. The first explanation of this difference is the level of turbulent buffeting forces to which the tube bundle is exposed. Increased values of turbulence will lower the void fraction for instability. The second explanation is related to the flow regime. In this study, it was clear that flow regime for bundle void generation was at all times bubbly and homogeneous, while the upstream void fraction generation cases showed a clear tendency to churn flow. A change in flow regime from bubbly to churn flow will produce the same effect as an increase in turbulence buffeting levels, and hence it seems difficult with the present knowledge to distinguish between the two causes. In as much as turbulence levels are related to flow regime, it is essential to have a clear knowledge of the flow regime in steam generators in order to predict the fluidelastic instability threshold of the tubes.
机译:核蒸汽发生器管束的U形弯曲区域遭受两相错流引起的振动。该区域的管子经历了高振幅的振动,导致灾难性的故障。湍流抖振和流体弹性的不稳定性已被确定为主要原因。先前的研究集中在流态和两相流阻尼比上。然而,蒸汽发生器中的管束在管的表面产生了蒸汽,这可能会影响流动状态,空隙率分布,湍流水平和管-流相互作用,所有这些都可能改变管的振动响应。构造了一个由电热筒加热器制成的悬臂式管束,并在Freon-11流动回路中进行了测试。管以节距与直径之比为1.48的平行三角形配置。该管束暴露于两相错流,该两相交叉流由来自两个源的空隙的不同组合,在管束上游产生的空隙和在管子表面处产生的空隙组成。用光学方法测量管头的振动响应,并用伽马密度法测量空隙率。与仅在上游产生空隙的情况下所观察到的响应相比,发现对于仅在管表面产生的空隙率,在横向方向上的管振动振幅的比率减小了8倍。对此影响的主要解释是减小了湍流抖振强迫函数的相关长度。在相同的实验条件下,由于湍流抖振而引起的管振动响应的理论计算预测出管幅值也有类似的减小。在存在管束空隙分数的情况下,流体弹性不稳定性阈值的空隙分数高于上游空隙分数的产生情况。对此差异的第一个解释是管束所承受的湍流抖振力水平。湍流值的增加将降低空隙率,从而导致不稳定。第二种解释与流动状态有关。在这项研究中,很明显,束空洞产生的流动方式始终是气泡状且均匀的,而上游空洞分数产生的情况则显示出明显的搅动流动趋势。从泡状流向搅动流的流动方式的变化将产生与湍流抖振水平增加相同的效果,因此,根据目前的知识,似乎很难区分这两种原因。由于湍流水平与流动状态有关,因此必须对蒸汽发生器的流动状态有清楚的了解,以便预测管子的流体弹性不稳定性阈值。

著录项

  • 作者

    Gidi, Alejandro.;

  • 作者单位

    McMaster University (Canada).;

  • 授予单位 McMaster University (Canada).;
  • 学科 Engineering Mechanical.; Energy.
  • 学位 Ph.D.
  • 年度 2000
  • 页码 255 p.
  • 总页数 255
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 机械、仪表工业;能源与动力工程;
  • 关键词

  • 入库时间 2022-08-17 11:47:42

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