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    Low Cycle Fatigue and Creep Fatigue Behavior of Alloy 617 at High Temperature

    Source: Journal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 006::page 61401
    Author:
    Cabet, Celine
    ,
    Carroll, Laura
    ,
    Wright, Richard
    DOI: 10.1115/1.4025080
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Alloy 617 is the leading candidate material for an intermediate heat exchanger (IHX) application of the very high temperature nuclear reactor (VHTR), expected to have an outlet temperature as high as 950 آ°C. Acceptance of Alloy 617 in Section III of the ASME Code for nuclear construction requires a detailed understanding of the creepfatigue behavior. Initial creepfatigue work on Alloy 617 suggests a more dominant role of environment with increasing temperature and/or hold times evidenced through changes in creepfatigue crack growth mechanisms and failure life. Continuous cycle fatigue and creepfatigue testing of Alloy 617 was conducted at 950 آ°C and 0.3% and 0.6% total strain in air to simulate damage modes expected in a VHTR application. Continuous cycle fatigue specimens exhibited transgranular cracking. Intergranular cracking was observed in the creepfatigue specimens and the addition of a hold time at peak tensile strain degraded the cycle life. This suggests that creepfatigue interaction occurs and that the environment may be partially responsible for accelerating failure.
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      Low Cycle Fatigue and Creep Fatigue Behavior of Alloy 617 at High Temperature

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    https://yetl.yabesh.ir/yetl1/handle/yetl/153112
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    contributor authorCabet, Celine
    contributor authorCarroll, Laura
    contributor authorWright, Richard
    date accessioned2017-05-09T01:02:30Z
    date available2017-05-09T01:02:30Z
    date issued2013
    identifier issn0094-9930
    identifier otherpvt_135_06_061401.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/153112
    description abstractAlloy 617 is the leading candidate material for an intermediate heat exchanger (IHX) application of the very high temperature nuclear reactor (VHTR), expected to have an outlet temperature as high as 950 آ°C. Acceptance of Alloy 617 in Section III of the ASME Code for nuclear construction requires a detailed understanding of the creepfatigue behavior. Initial creepfatigue work on Alloy 617 suggests a more dominant role of environment with increasing temperature and/or hold times evidenced through changes in creepfatigue crack growth mechanisms and failure life. Continuous cycle fatigue and creepfatigue testing of Alloy 617 was conducted at 950 آ°C and 0.3% and 0.6% total strain in air to simulate damage modes expected in a VHTR application. Continuous cycle fatigue specimens exhibited transgranular cracking. Intergranular cracking was observed in the creepfatigue specimens and the addition of a hold time at peak tensile strain degraded the cycle life. This suggests that creepfatigue interaction occurs and that the environment may be partially responsible for accelerating failure.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleLow Cycle Fatigue and Creep Fatigue Behavior of Alloy 617 at High Temperature
    typeJournal Paper
    journal volume135
    journal issue6
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4025080
    journal fristpage61401
    journal lastpage61401
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 006
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
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