YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    View Item 
    •   YE&T Library
    • ASME
    • Journal of Nuclear Engineering and Radiation Science
    • View Item
    •   YE&T Library
    • ASME
    • Journal of Nuclear Engineering and Radiation Science
    • View Item
    • All Fields
    • Source Title
    • Year
    • Publisher
    • Title
    • Subject
    • Author
    • DOI
    • ISBN
    Advanced Search
    JavaScript is disabled for your browser. Some features of this site may not work without it.

    Archive

    Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002::page 21003
    Author:
    Kinoshita, Ikuo
    ,
    Torige, Toshihide
    ,
    Yamada, Minoru
    DOI: 10.1115/1.4031377
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Interfacial friction in the core affects the twophase mixture level and the distribution of the dispersed gas phase during a smallbreak lossofcoolant accident (LOCA). The RELAP5/MOD3.2 code uses the drift flux model to describe the interfacial friction force in vertical dispersed flow, and the Chexal–Lellouche drift flux correlation is used for the rod bundle geometry. In the present study, the RELAP5 model uncertainty was quantified for the bubbly–slug interfacial friction model in the rod bundle geometry by conducting numerical analyses of void profile tests in the Thermal Hydraulic Test Facility (THTF) of the Oak Ridge National Laboratory (ORNL). The model uncertainty parameter was defined as a multiplier for the interfacial friction coefficient. Numerical analyses were performed by adjusting the multiplier so that the predicted void fractions agreed with the measured test data. The resultant distribution of the multipliers represented the interfacial friction model uncertainty.
    • Download: (1.828Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Price: 5000 Rial
    • Statistics

      Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/162194
    Collections
    • Journal of Nuclear Engineering and Radiation Science

    Show full item record

    contributor authorKinoshita, Ikuo
    contributor authorTorige, Toshihide
    contributor authorYamada, Minoru
    date accessioned2017-05-09T01:32:11Z
    date available2017-05-09T01:32:11Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_2_021003.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162194
    description abstractInterfacial friction in the core affects the twophase mixture level and the distribution of the dispersed gas phase during a smallbreak lossofcoolant accident (LOCA). The RELAP5/MOD3.2 code uses the drift flux model to describe the interfacial friction force in vertical dispersed flow, and the Chexal–Lellouche drift flux correlation is used for the rod bundle geometry. In the present study, the RELAP5 model uncertainty was quantified for the bubbly–slug interfacial friction model in the rod bundle geometry by conducting numerical analyses of void profile tests in the Thermal Hydraulic Test Facility (THTF) of the Oak Ridge National Laboratory (ORNL). The model uncertainty parameter was defined as a multiplier for the interfacial friction coefficient. Numerical analyses were performed by adjusting the multiplier so that the predicted void fractions agreed with the measured test data. The resultant distribution of the multipliers represented the interfacial friction model uncertainty.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
    typeJournal Paper
    journal volume2
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4031377
    journal fristpage21003
    journal lastpage21003
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002
    contenttypeFulltext
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian
     
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian