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    Effects of Initial Crack Location on Failure Assessment Curves in Dissimilar Metal Weld Joints in Nuclear Power Plants

    Source: Journal of Pressure Vessel Technology:;2012:;volume( 134 ):;issue: 006::page 61405
    Author:
    N. Gong
    ,
    G. Z. Wang
    ,
    F. Z. Xuan
    ,
    S. T. Tu
    DOI: 10.1115/1.4006907
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Based on detailed three-dimensional finite element analyses, accurate, option 3, failure assessment curves (FACs) based on the R6 are constructed for a dissimilar metal weld joint (DMWJ) connecting the safe end to the pipe-nozzle of a reactor pressure vessel. The effects of initial crack location in the DMWJ structure on FACs are investigated. The results show that the plastic collapse of the DMWJ structure and the limit moment ML is mainly dominated by the plastic yield of the 316L material with lowest yield stress, and the crack locations in the DMWJ structure have less effect on the ML. When the load ratio Lr is less than 0.8, the crack locations have almost no effect on the FACs; while after the Lr is larger than 0.8, the crack locations have significant effect on the FACs. With the crack location moving from the safe end through the DMWJ toward the thickness transition in the pipe-nozzle, the FACs shift upward, which leads to a enlargement of the safe region in the failure assessment diagrams (FADs). This is mainly caused by the different properties of the materials in the DMWJ structure. To accurately assess the integrity of the DMWJ structure, the R6 option 3 FACs based on three-dimensional finite element analyses should be constructed and used for the cracks with different positions.
    keyword(s): Fracture (Materials) , Nozzles , Pipes , Failure , Metals , Stress AND Nuclear power stations ,
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      Effects of Initial Crack Location on Failure Assessment Curves in Dissimilar Metal Weld Joints in Nuclear Power Plants

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    http://yetl.yabesh.ir/yetl1/handle/yetl/150053
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    contributor authorN. Gong
    contributor authorG. Z. Wang
    contributor authorF. Z. Xuan
    contributor authorS. T. Tu
    date accessioned2017-05-09T00:53:54Z
    date available2017-05-09T00:53:54Z
    date copyright41244
    date issued2012
    identifier issn0094-9930
    identifier otherJPVTAS-926532#pvt_134_6_061405.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/150053
    description abstractBased on detailed three-dimensional finite element analyses, accurate, option 3, failure assessment curves (FACs) based on the R6 are constructed for a dissimilar metal weld joint (DMWJ) connecting the safe end to the pipe-nozzle of a reactor pressure vessel. The effects of initial crack location in the DMWJ structure on FACs are investigated. The results show that the plastic collapse of the DMWJ structure and the limit moment ML is mainly dominated by the plastic yield of the 316L material with lowest yield stress, and the crack locations in the DMWJ structure have less effect on the ML. When the load ratio Lr is less than 0.8, the crack locations have almost no effect on the FACs; while after the Lr is larger than 0.8, the crack locations have significant effect on the FACs. With the crack location moving from the safe end through the DMWJ toward the thickness transition in the pipe-nozzle, the FACs shift upward, which leads to a enlargement of the safe region in the failure assessment diagrams (FADs). This is mainly caused by the different properties of the materials in the DMWJ structure. To accurately assess the integrity of the DMWJ structure, the R6 option 3 FACs based on three-dimensional finite element analyses should be constructed and used for the cracks with different positions.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEffects of Initial Crack Location on Failure Assessment Curves in Dissimilar Metal Weld Joints in Nuclear Power Plants
    typeJournal Paper
    journal volume134
    journal issue6
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4006907
    journal fristpage61405
    identifier eissn1528-8978
    keywordsFracture (Materials)
    keywordsNozzles
    keywordsPipes
    keywordsFailure
    keywordsMetals
    keywordsStress AND Nuclear power stations
    treeJournal of Pressure Vessel Technology:;2012:;volume( 134 ):;issue: 006
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
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