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    Wear Studies of Materials for Tubes and Antivibration Bars in Nuclear Steam Generators

    Source: Journal of Pressure Vessel Technology:;1996:;volume( 118 ):;issue: 003::page 287
    Author:
    P. L. Ko
    ,
    M.-C. Taponat
    ,
    M. Zbinden
    DOI: 10.1115/1.2842191
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Wear occurs as a result of relative motion at the interface of two contacting bodies. In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in wear damage due to impact and sliding contacts between the tubes and their supports. A research project aiming to gain better understanding of the mechanisms and mechanics involved in vibratory wear and to develop a more versatile predictive wear model was carried out. Combinations of Inconel tubes against flat antivibration bars of 403 SS and electrolytic-chrome plated Inconel 600 were tested under conditions of reciprocating sliding and impacting in water at room temperature and at 250°C. The results show that, depending on the material combinations and he loading conditions, distinctively different wear mechanisms and often drastically different wear rates can occur.
    keyword(s): Wear , Nuclear reactor steam generators , Mechanisms , Flow (Dynamics) , Water , Temperature , Motion , Boilers , Vibration AND Nuclear power ,
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      Wear Studies of Materials for Tubes and Antivibration Bars in Nuclear Steam Generators

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/117536
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    contributor authorP. L. Ko
    contributor authorM.-C. Taponat
    contributor authorM. Zbinden
    date accessioned2017-05-08T23:51:21Z
    date available2017-05-08T23:51:21Z
    date copyrightAugust, 1996
    date issued1996
    identifier issn0094-9930
    identifier otherJPVTAS-28369#287_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/117536
    description abstractWear occurs as a result of relative motion at the interface of two contacting bodies. In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in wear damage due to impact and sliding contacts between the tubes and their supports. A research project aiming to gain better understanding of the mechanisms and mechanics involved in vibratory wear and to develop a more versatile predictive wear model was carried out. Combinations of Inconel tubes against flat antivibration bars of 403 SS and electrolytic-chrome plated Inconel 600 were tested under conditions of reciprocating sliding and impacting in water at room temperature and at 250°C. The results show that, depending on the material combinations and he loading conditions, distinctively different wear mechanisms and often drastically different wear rates can occur.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleWear Studies of Materials for Tubes and Antivibration Bars in Nuclear Steam Generators
    typeJournal Paper
    journal volume118
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2842191
    journal fristpage287
    journal lastpage300
    identifier eissn1528-8978
    keywordsWear
    keywordsNuclear reactor steam generators
    keywordsMechanisms
    keywordsFlow (Dynamics)
    keywordsWater
    keywordsTemperature
    keywordsMotion
    keywordsBoilers
    keywordsVibration AND Nuclear power
    treeJournal of Pressure Vessel Technology:;1996:;volume( 118 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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