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    Risk Analysis of Reactor Pressure Vessels Considering Modeling-Induced Uncertainties

    Source: Journal of Verification, Validation and Uncertainty Quantification:;2016:;volume( 001 ):;issue: 004::page 41005
    Author:
    Riley, Matthew E.
    ,
    Hoffman, William M.
    DOI: 10.1115/1.4035444
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Uncertainties in simulation models arise not only from the parameters that are used within the model, but also due to the modeling process itself—specifically the identification of a model that most accurately predicts the true physical response of interest. In risk-analysis studies, it is critical to consider the effect that all forms of uncertainty have on the overall level of uncertainty. This work develops an approach to quantify the effect of both parametric and model-form uncertainties. The developed approach is demonstrated on the assessment of the fatigue-based risk associated with a reactor pressure vessel subjected to a thermal shock event.
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      Risk Analysis of Reactor Pressure Vessels Considering Modeling-Induced Uncertainties

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    contributor authorRiley, Matthew E.
    contributor authorHoffman, William M.
    date accessioned2017-11-25T07:20:00Z
    date available2017-11-25T07:20:00Z
    date copyright2017/01/12
    date issued2016
    identifier issn2377-2158
    identifier othervvuq_001_04_041005.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4236159
    description abstractUncertainties in simulation models arise not only from the parameters that are used within the model, but also due to the modeling process itself—specifically the identification of a model that most accurately predicts the true physical response of interest. In risk-analysis studies, it is critical to consider the effect that all forms of uncertainty have on the overall level of uncertainty. This work develops an approach to quantify the effect of both parametric and model-form uncertainties. The developed approach is demonstrated on the assessment of the fatigue-based risk associated with a reactor pressure vessel subjected to a thermal shock event.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleRisk Analysis of Reactor Pressure Vessels Considering Modeling-Induced Uncertainties
    typeJournal Paper
    journal volume1
    journal issue4
    journal titleJournal of Verification, Validation and Uncertainty Quantification
    identifier doi10.1115/1.4035444
    journal fristpage41005
    journal lastpage041005-10
    treeJournal of Verification, Validation and Uncertainty Quantification:;2016:;volume( 001 ):;issue: 004
    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
    yabeshDSpacePersian