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

    Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003::page 30905-1
    Author:
    Wu, Jason H.
    ,
    Beuthe, Thomas G.
    ,
    Vasić, Aleksandar
    DOI: 10.1115/1.4062917
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Small modular reactors (SMRs) are actively being considered for use in Canada. Some proposed SMRs can make use of solar salt as an intermediate coolant for a heat storage system. The development of thermalhydraulic simulation tools is one of the key capabilities needed to examine the performance of SMRs and license this class of reactors. This article summarizes the implementation of molten solar salt fluid properties into the algorithm for analysis of network thermalhydraulics (ARIANT) and uses this code to simulate a high temperature gas-cooled SMR with helium and solar salt as its primary and secondary coolants during a pressurized loss of forced circulation (PLOFC) event. This work demonstrates the ability of ARIANT to simulate transient events in a two-loop reactor system consisting of helium and solar salt as coolants and helps to establish ARIANT as a tool for SMR analysis.
    • Download: (1.544Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Price: 5000 Rial
    • Statistics

      Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/4295752
    Collections
    • Journal of Nuclear Engineering and Radiation Science

    Show full item record

    contributor authorWu, Jason H.
    contributor authorBeuthe, Thomas G.
    contributor authorVasić, Aleksandar
    date accessioned2024-04-24T22:43:23Z
    date available2024-04-24T22:43:23Z
    date copyright3/8/2024 12:00:00 AM
    date issued2024
    identifier issn2332-8983
    identifier otherners_010_03_030905.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295752
    description abstractSmall modular reactors (SMRs) are actively being considered for use in Canada. Some proposed SMRs can make use of solar salt as an intermediate coolant for a heat storage system. The development of thermalhydraulic simulation tools is one of the key capabilities needed to examine the performance of SMRs and license this class of reactors. This article summarizes the implementation of molten solar salt fluid properties into the algorithm for analysis of network thermalhydraulics (ARIANT) and uses this code to simulate a high temperature gas-cooled SMR with helium and solar salt as its primary and secondary coolants during a pressurized loss of forced circulation (PLOFC) event. This work demonstrates the ability of ARIANT to simulate transient events in a two-loop reactor system consisting of helium and solar salt as coolants and helps to establish ARIANT as a tool for SMR analysis.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleImplementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor
    typeJournal Paper
    journal volume10
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4062917
    journal fristpage30905-1
    journal lastpage30905-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003
    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