A5045852286- Nuclear Materials and Properties
- Fusion materials and technologies
- Additive Manufacturing Materials and Processes
- Hydrogen embrittlement and corrosion behaviors in metals
- High Entropy Alloys Studies
- High-Temperature Coating Behaviors
- Microstructure and mechanical properties
- High Temperature Alloys and Creep
- Ion-surface interactions and analysis
- Nuclear materials and radiation effects
- Additive Manufacturing and 3D Printing Technologies
- Welding Techniques and Residual Stresses
- Mycotoxins in Agriculture and Food
- Advanced materials and composites
- Advanced Materials Characterization Techniques
- Microstructure and Mechanical Properties of Steels
- Metal and Thin Film Mechanics
- Intermetallics and Advanced Alloy Properties
- Metallurgy and Material Forming
- Aluminum Alloys Composites Properties
- RNA modifications and cancer
- Metallic Glasses and Amorphous Alloys
- Nuclear reactor physics and engineering
- Metal Forming Simulation Techniques
- Diamond and Carbon-based Materials Research
Shanghai Jiao Tong University
2022-2025
Qingdao University
2025
University of Michigan
2016-2024
Central South University
2024
Affiliated Hospital of Southwest Medical University
2021-2024
Southern Medical University
2024
Nanfang Hospital
2024
Gansu Agricultural University
2024
China University of Petroleum, East China
2023
Heilongjiang Academy of Sciences
2023
High energy particles introduce severe radiation damage in metallic materials, such as Ag. Here we report on the study twin boundary (TB) affected zone irradiated nanotwinned Ag wherein time accumulative defect density and diffusivity are substantially different from those interior. In situ studies also reveal surprising resilience self-healing of TBs response to radiation. This provides further support for design radiation-tolerant materials.
Irradiation assisted stress-corrosion cracking (IASCC) is a form of intergranular stress corrosion that occurs in irradiated austenitic alloys. It requires an microstructure along with high temperature water and stress. The process ubiquitous it wide range alloys chemistries, but only when the alloy irradiated. Despite evidence this degradation mode dates back to 1960s, mechanism by which has remained elusive. Here, using resolution electron backscattering detection analyze local...
The role of dislocations on ion irradiation-induced void formation is studied in a high-entropy alloy (HEA) NiCoFeCrPd. Despite previous observations that show alloys are swelling resistant due to high defect recombination rate, the enhanced with increasing density pre-existing at low strain levels shortened transient duration before onset swelling. Under certain irradiation conditions, may carry material closer sink-dominated regime. Compared another HEA NiCoFeCrMn, NiCoFeCrPd has smaller...