Kawamata Kiyohiro | Faculty Of Engineering Ibaraki University
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概要
関連著者
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Kurumada Akira
Faculty Of Engineering Ibaraki University
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Kawamata Kiyohiro
Faculty Of Engineering Ibaraki University
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KURUMADA Akira
Faculty of Engineering, Ibaraki University
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KAWAMATA Kiyohiro
Faculty of Engineering, Ibaraki University
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Oku Tatsuo
Faculty Of Engineering Ibaraki University
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Sato S
Department Of Physics Nagoya University
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Sato S
Inoue Superliquid Glass Project Exploratory Research For Advanced Technology Japan Science And Techn
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Sato Sennosuke
Faculty Of Engineering The University Of Ibaraki Hitachi.
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NODA Nobuaki
National Insitute for Fusion Science
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MOTOJIMA Osamu
National Insitute for Fusion Science
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Motojima Osamu
National Institute Of Fusion Science
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Noda Nobuaki
National Institute Of Fusion Science
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McENANEY Brian
Materials Science, University of Bath
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Kaneko Mitsunobu
Nuclear Fuel Industries Ltd. Tokai Works
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Ishida Ryohei
Dep. Of Mech. Eng. Faculty Of Eng. Univ. Of Osaka Prefecture
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Sato Sennosuke
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Kurumada Akira
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Kawamata Kiyohiro
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Mcenaney Brian
Materials Science University Of Bath
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SUZUKI Nobuyuki
Nuclear Fuel Industries Ltd., Tokai Works
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Imamura Yoshio
Faculty Of Engineering Ibaraki University
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Deto Tatsuya
Ibaraki University
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Suzuki Shinichiro
Ibaraki University
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Ichikawa Masahiro
Ibaraki University
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Suzuki S
Ibaraki University
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Suzuki Nobuyuki
Nuclear Fuel Industries Ltd. Tokai Works
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ISHIDA Ryohei
Faculty of Engineering, University of Osaka Prefecture
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AWAJI Hideo
Japan Fine Ceramics Center
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SATO Sennosuke
Faculty of Engineering, Ibaraki University
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UGACHI Hirokazu
Faculty of Engineering, Ibaraki University
著作論文
- Thermal Shock Resistances of a Joining Material of C/C Composite and Copper
- Thermal Shock Resistances and the Irradiation Effects ot Graphites and C/C-Composites for Fusion Reactor Devices
- Neutron Irradiation Effects on Thermal Shock Resistances and Fracture Mechanical Properties of Fuel Compacts for the HTTR
- Effect of Neutron Irradiation on the Microstructures and Tensile Properties of Different Carbon Fibers
- Degradations of thermal shock resistance and fracture toughness of neutron irradiated reactor graphite.