Effects of Aluminum on the Corrosion Behavior of 16% Cr ODS Ferritic Steels in a Nitric Acid Solution
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概要
- 論文の詳細を見る
- 2011-02-01
著者
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Kasada Ryuta
Institute of Advanced Energy, Kyoto University
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Kimura Akihiko
Institute of Advanced Energy, Kyoto University
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Isselin Jerome
Institute of Advanced Energy, Kyoto University
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Kasada Ryuta
Institute Of Advanced Energy Kyoto University
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Kimura Akihiko
Institute Of Advanced Energy Kyoto University
-
Isselin Jerome
Institute Of Advanced Energy Kyoto University
関連論文
- Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel
- High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems : Nano-sized oxide dispersion strengthening steels
- Effects of aluminum on the corrosion behavior of 16% Cr ODS ferritic steels in a nitric acid solution
- Effects of Aluminum on the Corrosion Behavior of 16%Cr ODS Ferritic Steels in a Nitric Acid Solution
- Effects of Zr Addition on the Microstructure of 14%Cr4%Al ODS Ferritic Steels
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Precipitation Behavior of Irradiated Reduced-Activation Ferritic Steels
- Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel
- Mechanical Behavior of Oxide Dispersion Strengthened Steels Irradiated in JOYO
- Application of Small Punch Test to Evaluate Sigma-Phase Embrittlement of Pressure Vessel Cladding Material
- Effects of Aluminum on the Corrosion Behavior of 16% Cr ODS Ferritic Steels in a Nitric Acid Solution
- Factors Controlling Irradiation Hardening of Iron-Copper Model Alloy
- Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens
- PREFACE
- Effects of Nickel Addition on Microstructural Evolution and Mechanical Properties of Reduced Activation Martensitic Steels Irradiated in the ATR-A1
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Structure-Activity Relationship of the Warburgia Sesquiterpene Dialdehydes
- Irradiation Effect on Tensile Property of F82H IEA and Its Joint in TITAN Project