Tasaka Kanji | Department Of Nuclear Engineering Nagoya University
スポンサーリンク
概要
関連著者
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Tasaka Kanji
Department Of Nuclear Engineering Nagoya University
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Kukita Yutaka
Department Of Energy Engineering And Science Nagoya University
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Koizumi Yasuo
Department Of Mechanical Engineering Kogakuin University
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KUKITA Yutaka
Department of Energy Engineering & Science, Nagoya University
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NAKAMURA Hideo
Japan Atomic Energy Agency
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Nakamura Hideo
Department of Cardiovascular Medicine, Kyoto Prefectural University of Medicine
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HAGA Katsuhiro
Japan Atomic Energy Agency
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KUKITA Yutaka
Department of Energy Engineering and Science, Nagoya University
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Tasaka K
Department Of Nuclear Engineering Nagoya University
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Kukita Y
Department Of Energy Engineering And Science Nagoya University
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Kukita Yutaka
Department Of Nuclear Safety Research Japan Atomic Energy Research Institute
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Kukita Yutaka
Japan Atomic Energy Research Institute
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Kukita Y
Nagoya University
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HAGA Kazuko
Taiheiyo Consultant Co., Ltd.
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Haga K
Taiheiyo Consultant Co. Ltd.
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TASAKA Kanji
Department of Nuclear Engineering, Nagoya University
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Yonomoto Taisuke
Department Of Nuclear Safety Research Japan Atomic Energy Research Institute
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Nakamura Hideo
Department Of Cardiovascular Medicine Kyoto Prefectural University Of Medicine
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Nakamura Hideo
Nuclear Safety Research Center Japan Atomic Energy Agency
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Nakamura H
Nuclear Engineering Laboratory Toshiba Corporation
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Nakamura Hideo
Department Of Cardiology Kyoto Prefectural Yosanoumi Hospital
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Nakamura Hideo
Department Of Nuclear Safety Research Japan Atomic Energy Research Institute
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KOIZUMI Yasuo
Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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KUMAMARU Hiroshige
Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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KUMAMARU Hiroshige
Department of Nuclear Engineering, Faculty of Engineering, University of Tokyo
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KUKITA Yutaka
Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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TASAKA Kanji
Department of Reactor Safety Research, Japan Atomic Energy Research Institute
著作論文
- Interfacial Friction Factor for High-Pressure Steam/Water Stratified-Wavy Flow in Horizontal Pipe
- The Simulation Test to Start up the PIUS-Type Reactor from Isothermal Fluid Condition
- Onset criterion for liquid entrainment in reflooding phase of LOCA.
- Investigation of effect of pressure control system on BWR LOCA phenomena using ROSA-III test facility.