YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    View Item 
    •   YE&T Library
    • ASME
    • Journal of Pressure Vessel Technology
    • View Item
    •   YE&T Library
    • ASME
    • Journal of Pressure Vessel Technology
    • View Item
    • All Fields
    • Source Title
    • Year
    • Publisher
    • Title
    • Subject
    • Author
    • DOI
    • ISBN
    Advanced Search
    JavaScript is disabled for your browser. Some features of this site may not work without it.

    Archive

    Further Development of a Model for Predicting Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels

    Source: Journal of Pressure Vessel Technology:;1987:;volume( 109 ):;issue: 003::page 340
    Author:
    J. D. Gilman
    DOI: 10.1115/1.3264875
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Analysis of fatigue crack growth data for low-alloy steel shows that the influence of cyclic frequency in simulated LWR environments can be interpreted as the superposition of a time-dependent, corrosion-assisted crack growth rate upon an increment predicted by a Paris law. The time-dependent component increases monotonically to a maximum of about 6×10−5 mm/s as stress cycling becomes more aggressive. A useful measure of aggressiveness is the average time rate of crack advance due to the Paris law component alone; i.e., A ΔK n × frequency. The result suggests that current ASME Code methods for flaw assessment are highly conservative in some regimes of stress and frequency, but there is a possibility of growth rates well above the ASME XI, Appendix A curves in a very low-frequency, high-stress regime. An upper bound to the time rate of corrosion-assisted crack growth in low-alloy steel is well supported by the data. The threshold conditions for the onset of this high rate are less well defined and require further investigation.
    keyword(s): Steel , Fatigue cracks , Reactor vessels , Corrosion , Fracture (Materials) , Stress , Alloys , Light water reactors , ASME Standards AND Fatigue analysis ,
    • Download: (768.2Kb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Statistics

      Further Development of a Model for Predicting Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/102904
    Collections
    • Journal of Pressure Vessel Technology

    Show full item record

    contributor authorJ. D. Gilman
    date accessioned2017-05-08T23:25:31Z
    date available2017-05-08T23:25:31Z
    date copyrightAugust, 1987
    date issued1987
    identifier issn0094-9930
    identifier otherJPVTAS-28291#340_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/102904
    description abstractAnalysis of fatigue crack growth data for low-alloy steel shows that the influence of cyclic frequency in simulated LWR environments can be interpreted as the superposition of a time-dependent, corrosion-assisted crack growth rate upon an increment predicted by a Paris law. The time-dependent component increases monotonically to a maximum of about 6×10−5 mm/s as stress cycling becomes more aggressive. A useful measure of aggressiveness is the average time rate of crack advance due to the Paris law component alone; i.e., A ΔK n × frequency. The result suggests that current ASME Code methods for flaw assessment are highly conservative in some regimes of stress and frequency, but there is a possibility of growth rates well above the ASME XI, Appendix A curves in a very low-frequency, high-stress regime. An upper bound to the time rate of corrosion-assisted crack growth in low-alloy steel is well supported by the data. The threshold conditions for the onset of this high rate are less well defined and require further investigation.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleFurther Development of a Model for Predicting Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels
    typeJournal Paper
    journal volume109
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3264875
    journal fristpage340
    journal lastpage346
    identifier eissn1528-8978
    keywordsSteel
    keywordsFatigue cracks
    keywordsReactor vessels
    keywordsCorrosion
    keywordsFracture (Materials)
    keywordsStress
    keywordsAlloys
    keywordsLight water reactors
    keywordsASME Standards AND Fatigue analysis
    treeJournal of Pressure Vessel Technology:;1987:;volume( 109 ):;issue: 003
    contenttypeFulltext
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian
     
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian