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Axial-flow-induced vibration for a rod supported by translational springs at both ends

机译:两端由平移弹簧支撑的杆的轴流引起的振动

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摘要

An axial-flow-induced vibration model was proposed for a rod supported by two translational springs at both ends in order to evaluate the sensitivity to spring stiffness on the FIV for a PWR fuel rod. For developing the model, a one-mode approximation was made based on the assumption that the first mode was dominant in vibration behavior of the single span rod. The first natural frequency and mode shape functions for the flow-induced vibration, called the FIV, model were derived by using Lagrange's method. The vibration displacements were calculated by both of the spring-supported rod and the simple-supported (SS) one. As a result, the vibration displacement for the spring-supported (50 kN m~(-1)) rod was 15―20% larger than that of the SS rod when the rods are in axial flow of 5―8 m s~(-1) velocity. The discrepancy between both displacements became much larger as flow velocity increased, and that of the rod having the short span length was larger than that of the rod having the long span length although the displacement value itself of the long span rod was larger than that of the short one. The vibration displacement for the spring-supported rod appeared to decrease with the increase of the spring constant. Since single span beam supported by the two translational springs are focused on in this paper, further study will be needed to reflect more realistic supporting conditions of the PWR fuel rod such as two springs and four dimples and cross or swirling flow caused by the mixing vane of the spacer grid.
机译:为了评估PWR燃料棒在FIV上对弹簧刚度的敏感性,提出了一种在两端都由两个平移弹簧支撑的杆的轴向流引起的振动模型。为了开发模型,基于第一模态在单跨度杆的振动行为中占主导地位的假设,进行了单模近似。使用拉格朗日方法推导了流动振动的第一个固有频率和模态形状函数,称为FIV模型。通过弹簧支撑杆和简支杆(SS)计算振动位移。结果,弹簧支撑的(50 kN m〜(-1))杆的振动位移比SS杆的轴向位移为5〜8 ms〜(-时)大15〜20%。 1)速度。随着流速的增加,两个位移之间的差异变得更大,跨度较短的杆的位移值大于跨度较长的杆的位移,尽管长跨度杆本身的位移值大于滑杆长度的位移值。短的。弹簧支撑杆的振动位移随着弹簧常数的增加而减小。由于本文重点研究由两个平移弹簧支撑的单跨度梁,因此需要进一步研究以反映更实际的压水堆燃料棒支撑条件,例如两个弹簧和四个凹坑以及混合叶片引起的横流或涡流间隔格的角度。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2003年第1期|p.83-90|共8页
  • 作者单位

    Korea Atomic Energy Research Institute, Dukjin-dong 150, Yusung-Ku, Daejon 305-353, South Korea;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:48:56

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