Search Results - Murazaki, Minoru

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  1. 1
    Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs

    Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs by MURAZAKI, Minoru, TONOIKE, Kotaro, UCHIYAMA, Gunzo

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  2. 2
    Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

    Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems by Suyama, Kenya, Murazaki, Minoru, Ohkubo, Kiyoshi, Nakahara, Yoshinori, Uchiyama, Gunzo

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  3. 3
    Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs

    Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs by MURAZAKI, Minoru, TONOIKE, Kotaro, UCHIYAMA, Gunzo

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  4. 4
    Decreasing in neutron multiplication factor in spent fuel storage facilities by changing fuel assembly position in axial direction

    Decreasing in neutron multiplication factor in spent fuel storage facilities by changing fuel assembly position in axial direction by Suyama, Kenya, Murazaki, Minoru, Okuda, Yasuhisa

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  5. 5
    Active reduction of the end effect by local installation of neutron absorbers

    Active reduction of the end effect by local installation of neutron absorbers by Suyama, Kenya, Murazaki, Minoru, Ohkubo, Kiyoshi, Okuno, Hiroshi

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  6. 6
    Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel

    Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel by Sakai, Mikio, Yamamoto, Toshihiro, Murazaki, Minoru, Miyoshi, Yoshinori

    Published in Nuclear technology
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