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    Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 004::page 41008
    Author:
    Shimazaki, Yosuke
    ,
    Sawahata, Hiroaki
    ,
    Kawamoto, Taiki
    ,
    Suzuki, Hisashi
    ,
    Shinohara, Masanori
    ,
    Honda, Yuki
    ,
    Katsuyama, Kozo
    ,
    Takada, Shoji
    ,
    Sawa, Kazuhiro
    DOI: 10.1115/1.4032597
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Maintenance technologies for the reactor system have been developed by using the High Temperature engineering Test Reactor (HTTR). One of the important purposes of development is to accumulate the experiences and data to satisfy the availability of operation up to 90% by shortening the duration of the periodical maintenance for future high-temperature gas-cooled reactors (HTGRs) by shifting from time-based maintenance to condition-based maintenance. The technical issue of the maintenance of the in-core neutron detector, wide range monitor (WRM), is to predict the malfunction caused by cable disconnection to plan the replacement schedule. This is because it is difficult to observe directly inside the WRM in detail. The electrical inspection method was proposed to detect and predict the cable disconnection of the WRM by remote monitoring from outside the reactor using the time-domain reflectometry (TDR). The disconnection position, which was specified by the electrical method, was identified by nondestructive and destructive inspection. The accumulated data are expected to be contributed for advanced maintenance of future HTGRs.
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      Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4235381
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorShimazaki, Yosuke
    contributor authorSawahata, Hiroaki
    contributor authorKawamoto, Taiki
    contributor authorSuzuki, Hisashi
    contributor authorShinohara, Masanori
    contributor authorHonda, Yuki
    contributor authorKatsuyama, Kozo
    contributor authorTakada, Shoji
    contributor authorSawa, Kazuhiro
    date accessioned2017-11-25T07:18:45Z
    date available2017-11-25T07:18:45Z
    date copyright2016/10/12
    date issued2016
    identifier issn2332-8983
    identifier otherners_2_4_041008.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235381
    description abstractMaintenance technologies for the reactor system have been developed by using the High Temperature engineering Test Reactor (HTTR). One of the important purposes of development is to accumulate the experiences and data to satisfy the availability of operation up to 90% by shortening the duration of the periodical maintenance for future high-temperature gas-cooled reactors (HTGRs) by shifting from time-based maintenance to condition-based maintenance. The technical issue of the maintenance of the in-core neutron detector, wide range monitor (WRM), is to predict the malfunction caused by cable disconnection to plan the replacement schedule. This is because it is difficult to observe directly inside the WRM in detail. The electrical inspection method was proposed to detect and predict the cable disconnection of the WRM by remote monitoring from outside the reactor using the time-domain reflectometry (TDR). The disconnection position, which was specified by the electrical method, was identified by nondestructive and destructive inspection. The accumulated data are expected to be contributed for advanced maintenance of future HTGRs.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDevelopment of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors
    typeJournal Paper
    journal volume2
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4032597
    journal fristpage41008
    journal lastpage041008-5
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 004
    contenttypeFulltext
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