A5031327206- Nuclear Materials and Properties
- Hydrogen embrittlement and corrosion behaviors in metals
- High-Temperature Coating Behaviors
- Fatigue and fracture mechanics
- High Temperature Alloys and Creep
- Fusion materials and technologies
- Microstructure and Mechanical Properties of Steels
- Metal and Thin Film Mechanics
- Corrosion Behavior and Inhibition
- Advanced materials and composites
- Welding Techniques and Residual Stresses
- Metal Alloys Wear and Properties
- Nuclear reactor physics and engineering
- Nuclear and radioactivity studies
- Nuclear Engineering Thermal-Hydraulics
- Non-Destructive Testing Techniques
- Material Properties and Failure Mechanisms
- Metallurgical Processes and Thermodynamics
- Risk and Safety Analysis
- Graphite, nuclear technology, radiation studies
- High Entropy Alloys Studies
- Engineering Applied Research
- Microstructure and mechanical properties
- Aluminum Alloy Microstructure Properties
- Concrete Corrosion and Durability
Korea Advanced Institute of Science and Technology
2015-2024
National Cheng Kung University
2021
British Columbia Institute of Technology
2019
Chung-Ang University
2017-2019
Institute for Basic Science
2017
Korea Atomic Energy Research Institute
2017
Kyungpook National University
2017
Sejong University
2017
Chonnam National University
2017
Khalifa University of Science and Technology
2012
The oxidation behavior of three high-strength FeCrAl alloys was investigated in supercritical carbon dioxide environment at 650 °C. After exposure for 500 h, the weight gains gradually decreased with increasing Al content. oxide scales are primarily composed α-Al2O3 and spinel oxides. With content, amount increases C content scale sub-scale matrix. Moreover, larger (Nb,Mo)C carbides formed matrix their number increase