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    On Fatigue Design Curves for 2.25Cr-1Mo-V Steel Reactors at Elevated Temperature in Code Case 2605

    Source: Journal of Pressure Vessel Technology:;2018:;volume( 140 ):;issue: 002::page 21101
    Author:
    Gong, Jian-Guo
    ,
    Liu, Fang
    ,
    Xuan, Fu-Zhen
    DOI: 10.1115/1.4038903
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Fatigue design method for 2.25Cr-1Mo-V steel reactors in code case 2605 (CC 2605) is reviewed. Main factors such as the accelerating function of fatigue action, the cyclic frequency, the strain damage factor (β) related to the fatigue design curves are addressed, and the applicable stress level for pure creep rupture analysis in CC 2605 is also discussed. Results indicate that, for the high loading levels, the accelerating function of fatigue action and strain damage factor contribute relatively remarkably to the fatigue design curve. The increase of cyclic frequency leads to a remarkable increase of the allowable fatigue cycle number and hence reduces the conservativeness of fatigue design curve. It should be stipulated in CC 2605 that the applicable stress level is higher than a value of around 200 MPa (slightly dependent on temperature) for the adjusted uniaxial Omega damage parameter and 16 MPa for the creep strain rate when the Omega creep-damage method is employed.
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      On Fatigue Design Curves for 2.25Cr-1Mo-V Steel Reactors at Elevated Temperature in Code Case 2605

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4252789
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    contributor authorGong, Jian-Guo
    contributor authorLiu, Fang
    contributor authorXuan, Fu-Zhen
    date accessioned2019-02-28T11:06:42Z
    date available2019-02-28T11:06:42Z
    date copyright1/24/2018 12:00:00 AM
    date issued2018
    identifier issn0094-9930
    identifier otherpvt_140_02_021101.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252789
    description abstractFatigue design method for 2.25Cr-1Mo-V steel reactors in code case 2605 (CC 2605) is reviewed. Main factors such as the accelerating function of fatigue action, the cyclic frequency, the strain damage factor (β) related to the fatigue design curves are addressed, and the applicable stress level for pure creep rupture analysis in CC 2605 is also discussed. Results indicate that, for the high loading levels, the accelerating function of fatigue action and strain damage factor contribute relatively remarkably to the fatigue design curve. The increase of cyclic frequency leads to a remarkable increase of the allowable fatigue cycle number and hence reduces the conservativeness of fatigue design curve. It should be stipulated in CC 2605 that the applicable stress level is higher than a value of around 200 MPa (slightly dependent on temperature) for the adjusted uniaxial Omega damage parameter and 16 MPa for the creep strain rate when the Omega creep-damage method is employed.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleOn Fatigue Design Curves for 2.25Cr-1Mo-V Steel Reactors at Elevated Temperature in Code Case 2605
    typeJournal Paper
    journal volume140
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4038903
    journal fristpage21101
    journal lastpage021101-10
    treeJournal of Pressure Vessel Technology:;2018:;volume( 140 ):;issue: 002
    contenttypeFulltext
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