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    Vibration of a Tube Bundle in Two-Phase Freon Cross-Flow

    Source: Journal of Pressure Vessel Technology:;1995:;volume( 117 ):;issue: 004::page 321
    Author:
    M. J. Pettigrew
    ,
    J. H. Jong
    ,
    I. G. Currie
    ,
    C. E. Taylor
    DOI: 10.1115/1.2842130
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Two-phase cross-flow exists in many shell-and-tube heat exchangers. The U-bend region of nuclear steam generators is a prime example. Testing in two-phase flow simulated by air-water provides useful results inexpensively. However, two-phase flow parameters, in particular surface tension and density ratio, are considerably different in air-water than in steam-water. A reasonable compromise is testing in liquid-vapor Freon, which is much closer to steam-water while much simpler experimentally. This paper presents the first results of a series of tests on the vibration behavior of tube bundles subjected to two-phase Freon cross-flow. A rotated triangular tube bundle of tube-to-diameter ratio of 1.5 was tested over a broad range of void fractions and mass fluxes. Fluidelastic instability, random turbulence excitation, and damping were investigated. Well-defined fluidelastic instabilities were observed in continuous two-phase flow regimes. However, intermittent two-phase flow regimes had a dramatic effect on fluidelastic instability. Generally, random turbulence excitation forces are much lower in Freon than in air-water. Damping is very dependent on void fraction, as expected.
    keyword(s): Vibration , Cross-flow , Water , Two-phase flow , Testing , Steam , Turbulence , Damping , Heat exchangers , Flux (Metallurgy) , Density , Force , Surface tension , Vapors , Nuclear reactor steam generators , Porosity AND Shells ,
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      Vibration of a Tube Bundle in Two-Phase Freon Cross-Flow

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    http://yetl.yabesh.ir/yetl1/handle/yetl/115824
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    contributor authorM. J. Pettigrew
    contributor authorJ. H. Jong
    contributor authorI. G. Currie
    contributor authorC. E. Taylor
    date accessioned2017-05-08T23:48:07Z
    date available2017-05-08T23:48:07Z
    date copyrightNovember, 1995
    date issued1995
    identifier issn0094-9930
    identifier otherJPVTAS-28363#321_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/115824
    description abstractTwo-phase cross-flow exists in many shell-and-tube heat exchangers. The U-bend region of nuclear steam generators is a prime example. Testing in two-phase flow simulated by air-water provides useful results inexpensively. However, two-phase flow parameters, in particular surface tension and density ratio, are considerably different in air-water than in steam-water. A reasonable compromise is testing in liquid-vapor Freon, which is much closer to steam-water while much simpler experimentally. This paper presents the first results of a series of tests on the vibration behavior of tube bundles subjected to two-phase Freon cross-flow. A rotated triangular tube bundle of tube-to-diameter ratio of 1.5 was tested over a broad range of void fractions and mass fluxes. Fluidelastic instability, random turbulence excitation, and damping were investigated. Well-defined fluidelastic instabilities were observed in continuous two-phase flow regimes. However, intermittent two-phase flow regimes had a dramatic effect on fluidelastic instability. Generally, random turbulence excitation forces are much lower in Freon than in air-water. Damping is very dependent on void fraction, as expected.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleVibration of a Tube Bundle in Two-Phase Freon Cross-Flow
    typeJournal Paper
    journal volume117
    journal issue4
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2842130
    journal fristpage321
    journal lastpage329
    identifier eissn1528-8978
    keywordsVibration
    keywordsCross-flow
    keywordsWater
    keywordsTwo-phase flow
    keywordsTesting
    keywordsSteam
    keywordsTurbulence
    keywordsDamping
    keywordsHeat exchangers
    keywordsFlux (Metallurgy)
    keywordsDensity
    keywordsForce
    keywordsSurface tension
    keywordsVapors
    keywordsNuclear reactor steam generators
    keywordsPorosity AND Shells
    treeJournal of Pressure Vessel Technology:;1995:;volume( 117 ):;issue: 004
    contenttypeFulltext
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