Takeda T | Osaka Univ. Osaka
スポンサーリンク
概要
関連著者
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Takeda T
Osaka Univ. Osaka
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TAKEDA Toshikazu
Department of Urology, Keio University School of Medicine
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Takeda Toshikazu
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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Takeda Toshikazu
Department of Nuclear Energy, Graduate School of Engineering, Osaka University
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日引 俊
School of Nuclear Engineering, Purdue University
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日引 俊
School Of Nuclear Engineering Purdue University
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三島 嘉一郎
京大 原子炉実験所
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Hibiki Takashi
Research Reactor Institute Kyoto University
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MISHIMA Kaichiro
Research Reactor Institute, Kyoto University
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TATSUMI Masahiro
Department of Nuclear Engineering,Graduate School of Engineering,Osaka University
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GIHOU Akinori
Department of Nuclear Engineering,Graduate School of Engineering,Osaka University
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AMA Tsuyoshi
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
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HYOUDOU Hideaki
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
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TANAKA Futoshi
Graduate School of Energy Science, Kyoto University
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SAITO Yasushi
Research Reactor Institute, Kyoto University
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TAKEDA Tomoaki
Mitsubishi Heavy Industries, Ltd.
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Ama Tsuyoshi
Department Of Nuclear Energy Graduate School Of Engineering Osaka University
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Gihou Akinori
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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Tanaka Futoshi
Graduate School Of Energy Science Kyoto University
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Takeda T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
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Takeda Toshikazu
Nuclear Engineering Department Osaka University
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Tatsumi M
Nuclear Fuel Ind. Ltd. Osaka
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Takeda Tomoaki
Mitsubishi Heavy Industries Ltd.
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Hyoudou Hideaki
Department Of Nuclear Energy Graduate School Of Engineering Osaka University
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Mishima Kaichiro
Research Reactor Institute Kyoto University
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Saito Yasushi
Research Reactor Institute Kyoto University
著作論文
- Space and Angular Dependence of Interface Currents in the Multiband-CCCP Method
- Heat Transfer Study for Thermal-Hydraulic Design of the Soild-Target of Spallation Neutron Source
- Effect of Radial Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics