Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K
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概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 2003-04-25
著者
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NAGASE Fumihisa
Japan Atomic Energy Agency
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Nagase Fumihisa
Japan Atomic Energy Research Institute
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Uetsuka Hiroshi
Surface Chemistry Laboratory Kanagawa Academy Of Science And Technology Ksp East 404
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Uetsuka Hiroshi
Japan Atomic Energy Research Institute
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Uetsuka Hiroshi
Institute Of Materials Science University Of Tsukuba
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Uetsuka Hiroshi
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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Otomo Takashi
Japan Atomic Energy Research Institute
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Uetsuka H
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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- Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K
- B_4C/Zircaloy Reaction at Temperatures from 1, 173 to 1, 953 K
- Influence of Precipitated Hydride on the Fracture Behavior of Zircaloy Fuel Cladding Tube
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Oxidation kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1, 573 K
- Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions