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Vibrations in a 7-rod bundle subject to axial flow: Simulations and experiments

机译:7杆束中受轴流作用的振动:模拟和实验

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摘要

Being able to quantify mechanical vibrations is of key importance for the safety of nuclear power plants, as they are able to induce damage. In this work, numerical simulations are used to compute water flow and vibration in a densely packed bundle of 7 rods, mimicking an experimental setup. This flow configuration is chosen to resemble the coolant flow through a nuclear reactor core. Because of the wall proximity, a considerable velocity difference between the narrow gaps and the subchannels exists, with an inflection point in the velocity profile. This yields an unstable situation, and large vortices are continuously created through a mechanism similar to the Kelvin-Helmholtz instability. The vortex streets in between the rods are associated with a fluctuating pressure field, causing vibrations of the rods.The experimental setup contains 7 steel cylinders, encased in a hexagonal duct. The central rod contains a section where the steel is replaced by a water-filled silicone tube, clamped at both extremes to the steel rod, and the vibrations of this section are examined. The numerical approach consists of coupled fluid-structure interaction (FSI) simulations, with the flow being modelled using computational fluid dynamics (CFD) and the structure using computational solid mechanics (CSM).The available experimental data consist of Laser Doppler Anemometry (LDA) measurements and high-speed camera footage of the wall movement of the silicone rod. Equivalent data is collected from the numerical simulations. The simulations are repeated for different flow rates. The frequency spectrum of the coherent structures, and the frequency and amplitude of the wall movement are compared for each operating point, as well as their trend as a function of the flow rate. The dominant frequencies found in the simulation results were similar to the experimental results, although slightly higher. They also showed a linear trend, just like the experiments. A larger mismatch was present for the structural response, the frequencies found using the FSI model being more than twice as high.
机译:能够量化机械振动对于核电厂的安全至关重要,因为它们能够引起损害。在这项工作中,数值模拟用于计算密集堆积的7根棒束中的水流和振动,模仿了实验装置。选择该流动配置以类似于通过核反应堆堆芯的冷却剂流动。由于壁的接近性,在狭窄的间隙和子通道之间存在相当大的速度差,在速度曲线中具有拐点。这产生了不稳定的情况,并且通过类似于开尔文-亥姆霍兹不稳定性的机制连续产生大的涡旋。杆之间的涡流道与波动的压力场相关联,从而引起杆的振动。实验装置包含7个钢瓶,​​装在六角形管道中。中心杆包含一个区域,在该区域中,钢被充满水的硅树脂管所替代,并在两个极端处都夹在钢杆上,并检查了该部分的振动。数值方法由流固耦合模拟(FSI)组成,使用计算流体动力学(CFD)建模流动,并使用计算固体力学(CSM)建模结构。可用的实验数据包括激光多普勒风速仪(LDA)硅棒的壁运动的测量值和高速摄像机镜头。从数值模拟中收集等效数据。针对不同的流量重复进行模拟。比较每个工作点的相干结构的频谱以及壁运动的频率和幅度,以及它们作为流量函数的趋势。在模拟结果中发现的主导频率与实验结果相似,尽管略高。与实验一样,它们也显示出线性趋势。结构响应存在较大的不匹配,使用FSI模型发现的频率高出两倍以上。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2019年第11期|110227.1-110227.12|共12页
  • 作者单位

    Univ Ghent Dept Flow Heat & Combust Mech Sint Pietersnieuwstr 41 B-9000 Ghent Belgium;

    Delft Univ Technol Dept Radiat Sci & Technol Mekelweg 15 NL-2629 JB Delft Netherlands;

    Univ Ghent Dept Flow Heat & Combust Mech Sint Pietersnieuwstr 41 B-9000 Ghent Belgium|Flanders Make Lommel Belgium;

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

  • 入库时间 2022-08-18 05:00:39

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