Terminal Solid Solubility of Hydrogen in Unalloyed Zirconium by Differential Scanning Calorimetry

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概要

• 論文の詳細を見る
• 一般社団法人 日本原子力学会の論文
• 2004-09-25

著者

• ISHIMOTO Shinji

  Global Nuclear Fuel-Japan

• Une Katsumi

  Global Nuclear Fuel-japan Co. Ltd.

• Ishimoto Shinji

  Global Nuclear Fuel-japan Co. Ltd.

関連論文

• Effect of Hydrogen Water Chemistry on Zircaloy-2 Fuel Cladding and Structure Material Performance
• Heat Capacity Measurements of U_Gd_yO_2 (y=0-0.27) from 325 to 1,673K
• A New Non-destructive Technique for Hydrogen Level Assessment in Zirconium Alloys using EMAR Method
• Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter Diffraction
• Terminal Solid Solubility of Hydrogen in Unalloyed Zirconium by Differential Scanning Calorimetry
• Fission Gas Release Behavior from High Burnup UO_2 Fuels under Rapid Heating Conditions

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