YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    View Item 
    •   YE&T Library
    • ASME
    • Journal of Pressure Vessel Technology
    • View Item
    •   YE&T Library
    • ASME
    • Journal of Pressure Vessel Technology
    • 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

    Development of a Simplified Pressurized Water Reactor Fuel Assembly Nonlinear Model

    Source: Journal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 005::page 51304-1
    Author:
    Park, Namgyu
    ,
    Yoo, Youngik
    ,
    Kim, Taesoon
    ,
    Jeon, Sangyoun
    DOI: 10.1115/1.4053481
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper proposes a computation technique to develop a simplified nonlinear model for a typical nuclear fuel assembly. Because more than a hundred fuel assemblies are packed in the reactor, simplistic model generation is critical to evaluate the motion during an anticipated event such as earthquake. Two straight beams are introduced to simplify the fuel assembly, and the beam properties are moderately defined to represent the skeleton structure and a bundle of slender fuel rods. Because nonlinearity is caused by the interaction between the rods and the spacer grids in the skeleton structure, the two beams are connected with multilinear joints that characterize the mechanical interaction between them. An equation of motion for the model is provided, and the degree of the freedom of the model can be reduced by using a few major modes of the beams. Significant mechanical parameters must be defined reasonably, so a method is proposed to identify unknown parameters through a deterministic calculation and an optimization process. All the information, including the identified parameters, are utilized to develop a nonlinear finite element model with a commercial code. The performance of the model is compared with the test results.
    • Download: (1.339Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Statistics

      Development of a Simplified Pressurized Water Reactor Fuel Assembly Nonlinear Model

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/4284174
    Collections
    • Journal of Pressure Vessel Technology

    Show full item record

    contributor authorPark, Namgyu
    contributor authorYoo, Youngik
    contributor authorKim, Taesoon
    contributor authorJeon, Sangyoun
    date accessioned2022-05-08T08:39:28Z
    date available2022-05-08T08:39:28Z
    date copyright2/14/2022 12:00:00 AM
    date issued2022
    identifier issn0094-9930
    identifier otherpvt_144_05_051304.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284174
    description abstractThis paper proposes a computation technique to develop a simplified nonlinear model for a typical nuclear fuel assembly. Because more than a hundred fuel assemblies are packed in the reactor, simplistic model generation is critical to evaluate the motion during an anticipated event such as earthquake. Two straight beams are introduced to simplify the fuel assembly, and the beam properties are moderately defined to represent the skeleton structure and a bundle of slender fuel rods. Because nonlinearity is caused by the interaction between the rods and the spacer grids in the skeleton structure, the two beams are connected with multilinear joints that characterize the mechanical interaction between them. An equation of motion for the model is provided, and the degree of the freedom of the model can be reduced by using a few major modes of the beams. Significant mechanical parameters must be defined reasonably, so a method is proposed to identify unknown parameters through a deterministic calculation and an optimization process. All the information, including the identified parameters, are utilized to develop a nonlinear finite element model with a commercial code. The performance of the model is compared with the test results.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDevelopment of a Simplified Pressurized Water Reactor Fuel Assembly Nonlinear Model
    typeJournal Paper
    journal volume144
    journal issue5
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4053481
    journal fristpage51304-1
    journal lastpage51304-10
    page10
    treeJournal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 005
    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