Simple model for describing axial fission gas transport in fuel rod.
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概要
著者
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IWANO Yoshihiko
Nippon Nuclear Fuel Development Co., Ltd.
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HASHIZUME Kenichi
Faculty of Engineering, Kyushu University
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ITO Kenichi
Nippon Nuclear Fuel Development Co., Ltd,
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FURUYA Hirotaka
Faculty of Engineering, Kyushu University
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SUGISAKI Masayasu
Faculty of Engineering, Kyushu University
関連論文
- Thermal Conductivity of UO_2-BeO Pellet
- Magnetic Transition on Cooling Course for Ferromagnetic Metals
- Magnetic Transition on Cooling Course for Some Ferromagnetic,Ferrimagnetic and Antiferromagnetic Materials
- Finite Element Model for Analysis of Fission Gas Release from UO2 Fuel
- Simple model for describing axial fission gas transport in fuel rod.