2022 Annual Report
Interdiscipline
- Advanced Nuclear Material Research at the Laboratory of Nuclear Engineering Materials
- Precipitated-phase FeCrVTix Medium-entropy Alloys with Optimized Corrosion Resistance and Strength-ductility Synergy
- Structure and Fracture Behavior of Ion-beam-modified SiC-Al2O3-ZrO2 Ceramic Composites
- Phase Transitions and He Bubble Evolution in Ti3AlC2 under Sequential He Ion Implantation and Fe Ion Irradiation
- Helium Irradiation Induced Microstructural Damages and Mechanical Response of Al2O3-ZrO2-SiC Composites
- Beneficial Eect of Grain Refinement on the Oxidation Resistance of T91 Steel to Liquid Lead-bismuth Eutectic
- A Comparative Study of Proton Irradiation Responses of Three Candidate Materials for Proton Beam Windows: T91, SIMP Steel and Ti-6Al-4V
- Eect of Ti Addition on Microstructural Evolution, Strengthening and High Thermal Conductivity Mechanisms of FeCrV-based Medium-entropy Alloys
- Microstructure of TiAlN Coating after LBE Corrosion with Pre-irradiation
- Study on Thermal Conductivity of ZTA-SiCw Composites
- Influence of Temperature on Early-stage Corrosion of bcc Fe Surfaces in Oxygen Dissolved Liquid Lead-bismuth Eutectic (LBE-O)
- Irradiation Hardening Behavior of Long-term Thermal Ageing Martensitic Steel
- Ion Irradiation Effects on 4H-SiC Schottky Barrier Diodes
- Effect of Temperature on the Oxide Film of Austenitic Steel 15-15Ti in High-temperature CO2
- Surface Nanostructures and Formation Mechanism on TeO2 Induced by Swift Heavy Ions under Grazing Incidence
甘公网安备 62010202000713号
