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    Flow-Induced Vibration Analysis of an Integral Economizer Once-Through Steam Generator

    Source: Journal of Pressure Vessel Technology:;1989:;volume( 111 ):;issue: 004::page 501
    Author:
    M. K. Au-Yang
    ,
    B. Brenneman
    DOI: 10.1115/1.3265708
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The integral economizer once-through steam generator is a second-generation steam generator used in B&W’s 205-fuel assembly nuclear power plants. Besides having an integral economizer, this steam generator differs from the first generation units, sixteen of which have been operating with B&W’s 177 fuel assembly nuclear power plants for more than ten years, in having a much higher flow rate. This higher flow rate induces a correspondingly higher fluid-dynamic load on all of the steam generator internal components, particularly the tube bundle. This paper describes the flow-induced vibration design analysis of this second-generation nuclear steam generator. The three most commonly known flow-induced vibration phenomena were considered: fluid-elastic instability, turbulence-induced vibration and vortex-induced vibration. To minimize uncertainties in the many experimentally determined input parameters such as damping ratios, Connors’ constant and the dynamic pressure power spectral densities, a parallel analysis was carried out on the operating first-generation steam generator, and the results compared. The analytical results were verified by the recent start-up of B&W’s first 205-fuel assembly nuclear plant. No vibration problems were encountered during either the pre-operational test or in several months of full power operations.
    keyword(s): Boilers , Flow-induced vibrations , Nuclear power stations , Manufacturing , Fuels , Flow (Dynamics) , Fluids , Vibration , Nuclear reactor steam generators , Vortex-induced vibration , Pressure , Turbulence , Stress , Damping AND Design ,
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      Flow-Induced Vibration Analysis of an Integral Economizer Once-Through Steam Generator

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    https://yetl.yabesh.ir/yetl1/handle/yetl/105856
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    contributor authorM. K. Au-Yang
    contributor authorB. Brenneman
    date accessioned2017-05-08T23:30:48Z
    date available2017-05-08T23:30:48Z
    date copyrightNovember, 1989
    date issued1989
    identifier issn0094-9930
    identifier otherJPVTAS-28315#501_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/105856
    description abstractThe integral economizer once-through steam generator is a second-generation steam generator used in B&W’s 205-fuel assembly nuclear power plants. Besides having an integral economizer, this steam generator differs from the first generation units, sixteen of which have been operating with B&W’s 177 fuel assembly nuclear power plants for more than ten years, in having a much higher flow rate. This higher flow rate induces a correspondingly higher fluid-dynamic load on all of the steam generator internal components, particularly the tube bundle. This paper describes the flow-induced vibration design analysis of this second-generation nuclear steam generator. The three most commonly known flow-induced vibration phenomena were considered: fluid-elastic instability, turbulence-induced vibration and vortex-induced vibration. To minimize uncertainties in the many experimentally determined input parameters such as damping ratios, Connors’ constant and the dynamic pressure power spectral densities, a parallel analysis was carried out on the operating first-generation steam generator, and the results compared. The analytical results were verified by the recent start-up of B&W’s first 205-fuel assembly nuclear plant. No vibration problems were encountered during either the pre-operational test or in several months of full power operations.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleFlow-Induced Vibration Analysis of an Integral Economizer Once-Through Steam Generator
    typeJournal Paper
    journal volume111
    journal issue4
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3265708
    journal fristpage501
    journal lastpage506
    identifier eissn1528-8978
    keywordsBoilers
    keywordsFlow-induced vibrations
    keywordsNuclear power stations
    keywordsManufacturing
    keywordsFuels
    keywordsFlow (Dynamics)
    keywordsFluids
    keywordsVibration
    keywordsNuclear reactor steam generators
    keywordsVortex-induced vibration
    keywordsPressure
    keywordsTurbulence
    keywordsStress
    keywordsDamping AND Design
    treeJournal of Pressure Vessel Technology:;1989:;volume( 111 ):;issue: 004
    contenttypeFulltext
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