Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions
スポンサーリンク
概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 2003-02-25
著者
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Namekawa Takashi
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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SATO Isamu
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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HIROSAWA Takashi
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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MIYAHARA Sinya
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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Sato Isamu
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Miyahara Sinya
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Hirosawa Takashi
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Hirosawa Takashi
O-arai Engineering Center Japan Nuclear Cycle Development Institute
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Nakagiri Toshio
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
関連論文
- Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions
- Melting Temperature of Mixed Oxide Fuels for Fast Reactors
- Melting Temperature of Irradiated Fast Reactor Mixed Oxide Fuels
- Melting Temperature of Simulated High-Burnup Mixed Oxide Fuels for Fast Reactors
- Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions