OYAMA Akira | Department of Nuclear Engineering, Faculty of Engineering,the University of Tokyo
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概要
- OYAMA Akiraの詳細を見る
- 同名の論文著者
- Department of Nuclear Engineering, Faculty of Engineering,the University of Tokyoの論文著者
関連著者
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OYAMA Akira
Department of Nuclear Engineering, Faculty of Engineering,the University of Tokyo
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Oyama Akira
Department Of Space Transportation Engineering Institute Of Space And Astronautical Science Japan Ae
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AN Shigehiro
Department of Nuclear Engineering, Faculty of Engineering, University of Tokyo
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Kondo Shunsuke
Department Of Applied Chemistry Graduate School Of Engineering Nagoya University
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FUJII Kozo
Department of Cardiovascular Medicine, Yamaguchi University Graduate School of Medicine
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SHIMOYAMA Koji
Department of Aeronautics and Astronautics, University of Tokyo
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Fujii Kozo
Department Of Space Transportation Engineering Institute Of Space And Astronautical Science Japan Ae
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Shimoyama Koji
Department Of Aeronautics And Astronautics University Of Tokyo
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Fujiie Yoichi
Department Of Nuclear Engineering Faculty Of Engineering Osaka University
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AKIYAMA Mamoru
Department of Nuclear Engineering, Faculty of Engineering, University of Tokyo
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AKIYAMA Mamoru
Department of Nuclear Engineering, University of Tokyo
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TACHIBANA Fujio
Department of Nuclear Engineering, University of Tokyo
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MIYAGUCHI Kimihide
Plutonium Fuel Division, Power Reactor and Nuclear Fuel Development Corporation
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ASAHI Yoshiro
Department of Nuclear Engineering, University of Tokyo
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AN Shigehiro
Department of Nuclear Engineering, University of Tokyo
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FUJIIE Yoichi
Department of Nuclear Engineering, Faculty of Engineering,the University of Tokyo
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TACHIBANA Fujio
Department of Nuclear Engineering, Faculty of Engineering, University of Tokyo
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OYAMA Akira
Department of Nuclear Engineering, University of Tokyo
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SAITO Shinzo
Department of Nuclear Engineering, University of Tokyo
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TSAI Jensan
Department of Nuclear Engineering, University of Tokyo
著作論文
- New Constraint-Handling Method for Multi-Objective and Multi-Constraint Evolutionary Optimization
- Measurement of Heat Transfer Coefficients for Axial Air Flow through Eccentric Annulus and Seven-Rod Cluster
- A Simulation Experiment of the Results of Fission Product Gas Release due to Fuel Cladding Failure using Water Circulation System
- On the Two-Point Approximation Equation of Reactor Kinetics
- A Matrix Operator Method for Reactor Calculation
- Dynamic Analysis of Large Fast Reactor
- Effects of Multiple Control Rods