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

    Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

    Source: Journal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 006::page 61404
    Author:
    Wilhelm, Paul
    ,
    Rudolph, Jأ¼rgen
    ,
    Steinmann, Paul
    DOI: 10.1115/1.4029832
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A statistical model for austenitic stainless steels for predicting the effect of pressurized water reactor (PWR) environments on fatigue life for a range of temperatures and strain rates is developed based on analysis of available material data from USA, Europe, and Japan. Only fatigue data from polished specimens of wrought material tested under strain control were considered. Hollow specimens were not treated in the final calculations. The fatigue life correction factors were defined as the ratio of life in water at 300 آ°C (572 آ°F) (reference conditions) to that in water at service conditions. The model is recommended for predicting fatigue lives that are 103–105 cycles.
    • Download: (1.549Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Price: 5000 Rial
    • Statistics

      Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/159540
    Collections
    • Journal of Pressure Vessel Technology

    Show full item record

    contributor authorWilhelm, Paul
    contributor authorRudolph, Jأ¼rgen
    contributor authorSteinmann, Paul
    date accessioned2017-05-09T01:23:16Z
    date available2017-05-09T01:23:16Z
    date issued2015
    identifier issn0094-9930
    identifier otherpvt_137_06_061404.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159540
    description abstractA statistical model for austenitic stainless steels for predicting the effect of pressurized water reactor (PWR) environments on fatigue life for a range of temperatures and strain rates is developed based on analysis of available material data from USA, Europe, and Japan. Only fatigue data from polished specimens of wrought material tested under strain control were considered. Hollow specimens were not treated in the final calculations. The fatigue life correction factors were defined as the ratio of life in water at 300 آ°C (572 آ°F) (reference conditions) to that in water at service conditions. The model is recommended for predicting fatigue lives that are 103–105 cycles.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEffects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
    typeJournal Paper
    journal volume137
    journal issue6
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4029832
    journal fristpage61404
    journal lastpage61404
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 006
    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