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Indirect estimation method of the turbulence induced fluid force spectrum acting on a fuel rod

机译:间接作用于燃料棒上的湍流流体力谱的估计方法

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摘要

This paper proposes a methodology to identify a turbulent flow induced force acting on a nuclear fuel rod based on the indirect input force estimation theory in structural dynamics, which is useful to predict the forcing function when the input force cannot be measured directly. Since the nuclear fuel rod in a PWR (pressurized water reactor) is exposed to coolant flow, the turbulence induced force generates a fuel rod vibration which may cause a fretting wear on the surface of the rod. This study develops a method to estimate turbulence induced force spectrum indirectly for a real scale fuel rod loaded in a nuclear fuel test facility. The proposed method requires a reliable finite element (FE) model which simulates the fuel rod dynamics well; therefore, the FE model is discussed, especially regarding the procedure to determine the effective rod density. Since the pellets rattle inside the tube due to small gaps between the tube and pellets, especially at the beginning of the fuel's life, the contribution of the pellet mass to the density for the FE model cannot be determined clearly. It is shown that the appropriate density can be estimated by comparing the natural frequencies from the modal test results of the rod (with pellet) and the tube (without pellet). Then, the indirect turbulence induced force estimation theory is applied to the fuel rod, and some numerical and test results are discussed to verify the applicability of the suggested method.
机译:本文提出了一种基于结构动力学中的间接输入力估计理论来识别作用在核燃料棒上的湍流感应力的方法,该方法可用于预测无法直接测量输入力时的强迫函数。由于PWR(压水堆)中的核燃料棒暴露于冷却剂流,因此湍流引起的力会引起燃料棒振动,这可能会导致棒表面上的微动磨损。这项研究开发了一种方法,可以间接估算装在核燃料测试设施中的真实比例燃料棒的湍流感应力谱。所提出的方法需要可靠的有限元(FE)模型,该模型可以很好地模拟燃料棒动力学。因此,讨论了有限元模型,尤其是确定有效杆密度的程序。由于颗粒由于管和颗粒之间的小间隙而在管内发出嘎嘎声,特别是在燃料寿命开始时,因此,对于FE模型,颗粒质量对密度的贡献无法明确确定。结果表明,可以通过比较杆(带药丸)和管(无药丸)的模态测试结果中的固有频率来估算适当的密度。然后,将间接湍流感应力估计理论应用于燃料棒,并讨论了一些数值和测试结果,以验证该方法的适用性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2009年第7期|1237-1245|共9页
  • 作者单位

    R&D Center, Korea Nuclear Fuel, P.O. Box 14, Yuseong, Daejeon 305-353, Republic of Korea;

    Mechanical & Aerospace Engineering, Sunchon National University, 150 Maegok-dong, Sunchon 540-742, Republic of Korea;

    R&D Center, Korea Nuclear Fuel, P.O. Box 14, Yuseong, Daejeon 305-353, Republic of Korea;

    R&D Center, Korea Nuclear Fuel, P.O. Box 14, Yuseong, Daejeon 305-353, Republic of Korea;

    R&D Center, Korea Nuclear Fuel, P.O. Box 14, Yuseong, Daejeon 305-353, Republic of 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
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