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Numerical investigations on flow-induced vibration of fuel rods with spacer grids subjected to turbulent flow

机译:带有扰流的带间隔栅的燃料棒流致振动的数值研究

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摘要

Fuel rods, one of the most important parts in the nuclear reactor core, are usually supported by spacer grid along the axial flow direction. Since those fuel rods are surrounded by high-velocity coolant, vibration will be induced, termed flow-induced vibration (FIV). The resulting oscillations may cause abrasion of the cladding, known as fretting wear. In order to predict this fretting wear more accurately, it is essential to study the vibration characteristics. In this paper, numerical simulation is carried out to investigate the interaction of fuel rods embedded in a spacer grid with mixing vane subjected to strong turbulent flow. The flow-induced vibration of fuel rods and the surrounding components are analyzed and reported in detail. It is found that the vibration is dependent on several parameters, such as wall shear forces and pressure. However, the fluid force acting on the fuel rod is mostly due to the pressure. The flow velocity has a significant influence on the flow-induced vibration in axial turbulent flow. The vibration of fuel rod is very weak when the flow velocity is low. The numerical method applied in this paper can be used to predict the vibrations of the fuel rods accurately and this will be useful for the further fretting wear evaluating, which should be helpful in the design of fuel assemblies.
机译:燃料棒是核反应堆堆芯中最重要的部件之一,通常沿轴向流动方向由间隔栅支撑。由于那些燃料棒被高速冷却剂包围,因此将引起振动,称为流致振动(FIV)。产生的振动可能导致覆层磨损,称为微动磨损。为了更精确地预测微动磨损,研究振动特性至关重要。在本文中,进行了数值模拟,以研究嵌入在间隔栅中的燃料棒与混合叶片在强湍流作用下的相互作用。分析并报告了燃料棒和其周围组件的流动引起的振动。发现振动取决于几个参数,例如壁剪力和压力。然而,作用在燃料棒上的流体力主要是由于压力。流速对轴向湍流中的流动引起的振动有重大影响。当流速低时,燃料棒的振动非常弱。本文采用的数值方法可用于准确预测燃料棒的振动,这将有助于进一步评估微动磨损,这将有助于燃料组件的设计。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2017年第12期|68-77|共10页
  • 作者单位

    Chongqing Univ, Dept Power & Energy Engn, Chongqing 400044, Peoples R China;

    Chongqing Univ, Dept Power & Energy Engn, Chongqing 400044, Peoples R China;

    Chongqing Univ, Dept Power & Energy Engn, Chongqing 400044, Peoples R China;

    Nucl Power Inst China, CNNC Key Lab Nucl Reactor Thermal Hydraul Technol, Chengdu 610041, Peoples R China;

    Chongqing Univ, Dept Power & Energy Engn, Chongqing 400044, Peoples R China;

  • 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

    Flow-induced vibration (FIV); Fluid-structure interaction (FSI); Numerical simulation; Nuclear reactor;

    机译:流致振动(FIV);流固耦合(FSI);数值模拟;核反应堆;
  • 入库时间 2022-08-18 00:41:28

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