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    Weld Residual Stress in Various Large Diameter Nuclear Nozzles

    Source: Journal of Pressure Vessel Technology:;2012:;volume( 134 ):;issue: 006::page 61214
    Author:
    Tao Zhang
    ,
    Frederick W. Brust
    ,
    Gery Wilkowski
    DOI: 10.1115/1.4007036
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Weld residual stresses in nuclear power plants can lead to cracking concerns caused by stress corrosion. Many factors can lead to the development of the weld residual stresses, and the distributions of the stress through the wall thickness can vary markedly depending on the weld processing parameters, nozzle and pipe geometries, among other factors. Hence, understanding the residual stress distribution is important in order to evaluate the reliability of pipe and nozzle welded joints. This paper represents an examination of the weld residual stress distributions which occur in different nozzles. The geometries considered here are large diameter thick wall pipe and nozzles. The detailed weld residual stress predictions for these nozzles are summarized. These results are categorized and organized in this paper and general trends for the causes of the distributions are established. The solutions are obtained using several different constitutive models including kinematic hardening, isotropic hardening, and mixed hardening model. Necessary fabrication procedures such as weld repair, overlay, and postweld heat treatment are also considered. The residual stress field can therefore be used to perform a crack growth and instability analysis. Some general discussions and comments are given in the paper.
    keyword(s): Stress , Hardening , Nozzles , Overlays (Materials engineering) AND Residual stresses ,
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      Weld Residual Stress in Various Large Diameter Nuclear Nozzles

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    http://yetl.yabesh.ir/yetl1/handle/yetl/150048
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    contributor authorTao Zhang
    contributor authorFrederick W. Brust
    contributor authorGery Wilkowski
    date accessioned2017-05-09T00:53:53Z
    date available2017-05-09T00:53:53Z
    date copyright41244
    date issued2012
    identifier issn0094-9930
    identifier otherJPVTAS-926532#pvt_134_6_061214.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/150048
    description abstractWeld residual stresses in nuclear power plants can lead to cracking concerns caused by stress corrosion. Many factors can lead to the development of the weld residual stresses, and the distributions of the stress through the wall thickness can vary markedly depending on the weld processing parameters, nozzle and pipe geometries, among other factors. Hence, understanding the residual stress distribution is important in order to evaluate the reliability of pipe and nozzle welded joints. This paper represents an examination of the weld residual stress distributions which occur in different nozzles. The geometries considered here are large diameter thick wall pipe and nozzles. The detailed weld residual stress predictions for these nozzles are summarized. These results are categorized and organized in this paper and general trends for the causes of the distributions are established. The solutions are obtained using several different constitutive models including kinematic hardening, isotropic hardening, and mixed hardening model. Necessary fabrication procedures such as weld repair, overlay, and postweld heat treatment are also considered. The residual stress field can therefore be used to perform a crack growth and instability analysis. Some general discussions and comments are given in the paper.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleWeld Residual Stress in Various Large Diameter Nuclear Nozzles
    typeJournal Paper
    journal volume134
    journal issue6
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4007036
    journal fristpage61214
    identifier eissn1528-8978
    keywordsStress
    keywordsHardening
    keywordsNozzles
    keywordsOverlays (Materials engineering) AND Residual stresses
    treeJournal of Pressure Vessel Technology:;2012:;volume( 134 ):;issue: 006
    contenttypeFulltext
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