首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2007 >FLOW-INDUCED VIBRATION RESPONSES OF U-TUBE BUNDLE IN AIR-WATER FLOW
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FLOW-INDUCED VIBRATION RESPONSES OF U-TUBE BUNDLE IN AIR-WATER FLOW

机译:空气流中U型管束的流动引起的振动响应

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In the present study, a series of experiments have been performed to investigate a fluid-elastic instability of a nuclear steam generator U-tube bundle in an air-water two-phase flow condition. A total of 39 U-tubes are arranged in a rotated square array with a pitch-to-diameter ratio of 1.633. The diameter and other geometrical parameters of U-bend region are the same to those of an actual steam generator, but the vertical length of U-tubes are reduced to 2-span in contrast to 9-span of an actual steam generator. The following parameters were experimentally measured to evaluate a fluid-elastic instability of U-tube bundles in a two-phase flow: a general tube vibration response, a critical gap velocity, a damping ratio and a hydrodynamic mass. Based on the experimental measurements, the instability factor, K, of Connors' relation was preliminary assessed with some assumptions on the velocity and density profiles of the two-phase flow.
机译:在本研究中,已进行了一系列实验,以研究气水两相流条件下核蒸汽发生器U型管束的流体弹性不稳定性。总共39个U形管以旋转的方形阵列排列,螺距与直径之比为1.633。 U形弯曲区域的直径和其他几何参数与实际蒸汽发生器的直径和其他几何参数相同,但与实际蒸汽发生器的9个跨度相比,U型管的垂直长度减小到2个跨度。实验测量了以下参数,以评估两相流中U型管束的流体弹性不稳定性:总管振动响应,临界间隙速度,阻尼比和流体力学质量。在实验测量的基础上,对两相流的速度和密度分布进行了一些假设,初步评估了康纳斯关系的不稳定性因子K。

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