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    Post-Test Analyses of the CMMR-4 Test 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 002:;page 21701-1
    Author(s): Yamashita, Takuya; Madokoro, Hiroshi; Sato, Ikken
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Understanding the final distribution of core materials and their characteristics is important for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). Such characteristics depend on the accident progression ...
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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(s): Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro; Nagae, Yuji
    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 ...
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    Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002:;page 021113-1
    Author(s): Abe, Yuta; Yamashita, Takuya; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulant fuel material (ZrO2) that would contribute, not only to Fukushima Daiichi (1 F) decommissioning, but also ...
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