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    Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 20901
    Author:
    Abe, Yuta
    ,
    Sato, Ikken
    ,
    Nakagiri, Toshio
    ,
    Ishimi, Akihiro
    ,
    Nagae, Yuji
    DOI: 10.1115/1.4038911
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A new experimental program using nontransfer (NTR) type plasma heating is under consideration in Japan Atomic Energy Agency (JAEA) to clarify the uncertainty on core-material relocation (CMR) behavior of boiling water reactor (BWR). In order to confirm the applicability of this new technology, authors performed preparatory plasma heating tests using small-scale test pieces (107 mm × 107 mm × 222 mm (height)). An excellent perspective in terms of applicability of the NTR plasma heating to melting high melting-temperature materials such as ZrO2 has been obtained. In addition, molten pool was formed at the middle height of the test piece indicating its capability to simulate the initial phase of core degradation behavior consistent with the real UO2 fuel PHEBUS fission products (FP) tests. Furthermore, application of electron probe micro-analyzer (EPMA), scanning electron microscope (SEM)/energy dispersive X-ray spectrometry (EDX), and X-ray computed tomography (CT) led to a conclusion that the pool formed consisted mainly of Zr with some concentration of oxygen which tended to be enhanced at the upper surface region of the pool. Based on these results, an excellent perspective in terms of applicability of the NTR plasma heating technology to the severe accident (SA) experimental study was obtained.
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      Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4252538
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorAbe, Yuta
    contributor authorSato, Ikken
    contributor authorNakagiri, Toshio
    contributor authorIshimi, Akihiro
    contributor authorNagae, Yuji
    date accessioned2019-02-28T11:05:17Z
    date available2019-02-28T11:05:17Z
    date copyright3/5/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_02_020901.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252538
    description abstractA new experimental program using nontransfer (NTR) type plasma heating is under consideration in Japan Atomic Energy Agency (JAEA) to clarify the uncertainty on core-material relocation (CMR) behavior of boiling water reactor (BWR). In order to confirm the applicability of this new technology, authors performed preparatory plasma heating tests using small-scale test pieces (107 mm × 107 mm × 222 mm (height)). An excellent perspective in terms of applicability of the NTR plasma heating to melting high melting-temperature materials such as ZrO2 has been obtained. In addition, molten pool was formed at the middle height of the test piece indicating its capability to simulate the initial phase of core degradation behavior consistent with the real UO2 fuel PHEBUS fission products (FP) tests. Furthermore, application of electron probe micro-analyzer (EPMA), scanning electron microscope (SEM)/energy dispersive X-ray spectrometry (EDX), and X-ray computed tomography (CT) led to a conclusion that the pool formed consisted mainly of Zr with some concentration of oxygen which tended to be enhanced at the upper surface region of the pool. Based on these results, an excellent perspective in terms of applicability of the NTR plasma heating technology to the severe accident (SA) experimental study was obtained.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleApplication of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions
    typeJournal Paper
    journal volume4
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4038911
    journal fristpage20901
    journal lastpage020901-8
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
    contenttypeFulltext
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