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    Japanese Activities Concerning Nuclear Codes and Standards—Part I

    Source: Journal of Pressure Vessel Technology:;2006:;volume( 128 ):;issue: 001::page 57
    Author:
    Yasuhide Asada
    DOI: 10.1115/1.2138062
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part I of the series includes an overview, a discussion of administrative and design aspects related to new methods of evaluating the integrity of components, that is, piping seismic rules based on ratcheting fatigue, a fracture toughness equation for vessel materials, an extension of the Ke factor based on elastic follow-up, a discussion of high cycle thermal fatigue, and a three-dimensional finite element method elastic-plastic analysis procedure.
    keyword(s): Engineering standards , Stress , Design , Pipes , Cycles , Fatigue , Temperature , Nuclear power stations , Earthquakes , Evaluation methods AND Flow (Dynamics) ,
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      Japanese Activities Concerning Nuclear Codes and Standards—Part I

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    https://yetl.yabesh.ir/yetl1/handle/yetl/134554
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    contributor authorYasuhide Asada
    date accessioned2017-05-09T00:21:27Z
    date available2017-05-09T00:21:27Z
    date copyrightFebruary, 2006
    date issued2006
    identifier issn0094-9930
    identifier otherJPVTAS-28463#57_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/134554
    description abstractThis series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part I of the series includes an overview, a discussion of administrative and design aspects related to new methods of evaluating the integrity of components, that is, piping seismic rules based on ratcheting fatigue, a fracture toughness equation for vessel materials, an extension of the Ke factor based on elastic follow-up, a discussion of high cycle thermal fatigue, and a three-dimensional finite element method elastic-plastic analysis procedure.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleJapanese Activities Concerning Nuclear Codes and Standards—Part I
    typeJournal Paper
    journal volume128
    journal issue1
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2138062
    journal fristpage57
    journal lastpage63
    identifier eissn1528-8978
    keywordsEngineering standards
    keywordsStress
    keywordsDesign
    keywordsPipes
    keywordsCycles
    keywordsFatigue
    keywordsTemperature
    keywordsNuclear power stations
    keywordsEarthquakes
    keywordsEvaluation methods AND Flow (Dynamics)
    treeJournal of Pressure Vessel Technology:;2006:;volume( 128 ):;issue: 001
    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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