Experimental study of a flexible cantilever rod subjected to axial water flow

Chunyuan Liu, Andrea Cioncolini, Jorge Silva Leon, Dennis Cooper, Hector Iacovides

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    Abstract

    In industrial applications, fluid-structure interaction
    simulations often suffer from accuracy problems. For simulations
    to pressurized water nuclear reactor cores, such an accuracy level
    characterized by state-of-the-art simulation codes might require
    to be improved for safety concerns. One approach to solving the
    problem is through calibrations by high resolution experimental
    data. In this paper, a fluid-structure interaction system with
    close configurations as those in nuclear reactor cores is studied
    experimentally: a sealed cylindrical rod of stainless steel made,
    of 8.8/10 mm in I.D./O.D. and of 1.05 m in length is designed
    to be free at one end and fixed at the other end by mounting
    onto a coaxial Plexiglas tube. Through the annulus formed by
    the rod and the tube, turbulent water flows are directed from
    the free end to the fixed end of the rod. As the turbulent water
    axially flows by the rod, the rod tends to vibrate as a pressure
    difference across its cross section. From the experimental tests,
    the vibrating amplitude of the rod subjected to water flows was
    found to increase with Reynolds number, while the vibrating
    frequency is reduced. Under identical conditions, the rod with a
    blunt free-end had larger vibrating amplitude than that with a
    tapered free-end, and a lower vibrating frequency. The vibrating
    frequency of the rod was determined using both the free-end
    shape and the loading material.
    Original languageEnglish
    Title of host publicationMACE PGR Conference 2017
    Pages1-4
    Publication statusPublished - 1 Apr 2017

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