Fuel Pin Irradiation Test at up to 5 at% Burnup in BOR-60 for Oxide-Dispersion-Strengthened Ferritic Steel Claddings

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概要

• 論文の詳細を見る
• 社団法人 日本原子力学会の論文
• 2009-06-01

著者

• Ukai Shigeharu

  Japan Atomic Energy Agency

• Efimov Vladimir

  Research Institute Of Atomic Reactors State Scientific Center

• KAITO Takeji

  Japan Atomic Energy Agency

• POVSTYANKO Alexander

  Research Institute of Atomic Reactors, State Scientific Center

• Povstyanko Alexander

  Research Institute Of Atomic Reactors State Scientific Center

関連論文

• Fuel Pin Irradiation Test at up to 5 at% Burnup in BOR-60 for Oxide-Dispersion-Strengthened Ferritic Steel Claddings
• Preliminary Tube Manufacturing of Oxide Dispersion Strengthened Ferritic Steels with Recrystallized Structure
• Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
• Water Corrosion Resistance of ODS Ferritic-Martensitic Steel Tubes
• Kinetic Approach for Growth and Coalescence of Nano-Size Oxide Particles in 9Cr-ODS Steel Using High-Energy Synchrotron Radiation X-rays in SPring-8
• Thermal Conductivities of Granular UO_2 Compacts with/without Uranium Particles
• Recrystallization Texture of Cold-rolled Oxide Dispersion Strengthened Ferritic Steel

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