YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    View Item 
    •   YE&T Library
    • ASME
    • ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
    • View Item
    •   YE&T Library
    • ASME
    • ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
    • 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

    Machine Learning Approaches for Performance Assessment of Nuclear Fuel Assemblies Subject to Seismic-Induced Impacts

    Source: ASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg:;2020:;volume( 006 ):;issue: 004::page 041002-1
    Author:
    Altieri, Domenico
    ,
    Robin-Boudaoud, Marie-Cécile
    ,
    Kessler, Hannes
    ,
    Pellissetti, Manuel
    ,
    Patelli, Edoardo
    DOI: 10.1115/1.4046926
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In pressurized water nuclear reactors, the seismic performance of fuel assemblies is governed by their spacer grids (SGs) which may experience impacts with neighboring fuel assembly SGs or with the core barrel, depending on the intensity of the seismic event. Nonlinear dynamic analysis aiming at computing the maximum permanent deformation in a statistic framework is computationally demanding due to the different possible core configurations and the dimension of the dataset of seismic excitations. Hence, surrogate models trained by the physics-based dynamic model are proposed to analyze different scenarios, i.e., explore the space of potential core configurations and seismic excitations. Starting from ground motion records corresponding to six levels of seismic hazard, the dynamic excitation at the elevation of the reactor pressure vessel is obtained via transfer functions. Correlation between different seismic intensity measures and the maximum permanent deformation is evaluated. The performance of two well-established surrogate models, namely, artificial neural networks (ANN) and Gaussian process (GP) for regression problems is analyzed and discussed. Bayesian techniques are adopted to enhance the robustness of the trained surrogate models by training sets of neural networks and estimating the hyper-parameter of the GP.
    • Download: (2.215Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Price: 5000 Rial
    • Statistics

      Machine Learning Approaches for Performance Assessment of Nuclear Fuel Assemblies Subject to Seismic-Induced Impacts

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/4275327
    Collections
    • ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering

    Show full item record

    contributor authorAltieri, Domenico
    contributor authorRobin-Boudaoud, Marie-Cécile
    contributor authorKessler, Hannes
    contributor authorPellissetti, Manuel
    contributor authorPatelli, Edoardo
    date accessioned2022-02-04T22:19:05Z
    date available2022-02-04T22:19:05Z
    date copyright6/8/2020 12:00:00 AM
    date issued2020
    identifier issn2332-9017
    identifier otherrisk_006_04_041002.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275327
    description abstractIn pressurized water nuclear reactors, the seismic performance of fuel assemblies is governed by their spacer grids (SGs) which may experience impacts with neighboring fuel assembly SGs or with the core barrel, depending on the intensity of the seismic event. Nonlinear dynamic analysis aiming at computing the maximum permanent deformation in a statistic framework is computationally demanding due to the different possible core configurations and the dimension of the dataset of seismic excitations. Hence, surrogate models trained by the physics-based dynamic model are proposed to analyze different scenarios, i.e., explore the space of potential core configurations and seismic excitations. Starting from ground motion records corresponding to six levels of seismic hazard, the dynamic excitation at the elevation of the reactor pressure vessel is obtained via transfer functions. Correlation between different seismic intensity measures and the maximum permanent deformation is evaluated. The performance of two well-established surrogate models, namely, artificial neural networks (ANN) and Gaussian process (GP) for regression problems is analyzed and discussed. Bayesian techniques are adopted to enhance the robustness of the trained surrogate models by training sets of neural networks and estimating the hyper-parameter of the GP.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleMachine Learning Approaches for Performance Assessment of Nuclear Fuel Assemblies Subject to Seismic-Induced Impacts
    typeJournal Paper
    journal volume6
    journal issue4
    journal titleASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg
    identifier doi10.1115/1.4046926
    journal fristpage041002-1
    journal lastpage041002-7
    page7
    treeASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg:;2020:;volume( 006 ):;issue: 004
    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