A5001109941- Nuclear Materials and Properties
- Fusion materials and technologies
- High-Temperature Coating Behaviors
- Nuclear reactor physics and engineering
- Advanced materials and composites
- Radioactive element chemistry and processing
- High Entropy Alloys Studies
- Nuclear materials and radiation effects
- Additive Manufacturing Materials and Processes
- Metal and Thin Film Mechanics
- Molten salt chemistry and electrochemical processes
- Ion-surface interactions and analysis
- Powder Metallurgy Techniques and Materials
- Advanced Materials Characterization Techniques
- Injection Molding Process and Properties
- Concrete and Cement Materials Research
- Advanced ceramic materials synthesis
- Hydrogen embrittlement and corrosion behaviors in metals
- Drilling and Well Engineering
- Metallurgical Processes and Thermodynamics
- Metallurgy and Material Forming
- Tunneling and Rock Mechanics
- Corrosion Behavior and Inhibition
- Thermodynamic and Structural Properties of Metals and Alloys
- Metallurgical and Alloy Processes
University of Wisconsin–Madison
2019-2023
Brookhaven National Laboratory
2016-2022
British University in Egypt
2022
University of Illinois Urbana-Champaign
2010-2017
High-entropy alloys (HEAs) are a class of that can exhibit promising properties including enhanced irradiation resistance, high-temperature strength, and corrosion resistance. However, they exist in relatively unexplored region quasi-limitless composition space. Thus, to enable the development compositionally complex alloys, such as HEAs, high-throughput methods needed. Such capabilities developed presented this work. In situ alloying through additive manufacturing was employed produce...
The corrosion behavior of the FCC Cr18Mn27Fe27.5Ni27.5 high entropy alloy (HEA) after exposure to molten FLiBe salt at 700 °C for 1000 hours, has been investigated. Results show that HEA lost a higher mass compared reference 316 H stainless steel due dissolution Mn into salt. loss from appeared discourage Cr in fluoride salts which is widely recognized as mechanism degradation. Thermal hours also led precipitation an additional BCC phase Cr67Fe13Mn18.5Ni1.5, was confirmed by CALPHAD predictions.
Abstract The molten salt-cooled reactor concept has garnered significant interest and one of the current challenges limiting deployment these concepts is complex corrosion phenomenon observed in salt environments. One phenomena activity gradient mass transport, which been shown to affect dissimilar materials submerged same medium even when best efforts have made electrically isolate from another. This mechanism while experimentally, not predictively studied through a modeling approach. In...
A new in situ sample environment has been designed and developed to study the interfacial interactions of nuclear cladding alloys with high temperature steam. The is particularly optimized for synchrotron X-ray diffraction studies structural analysis. highly corrosion resistant can be readily adapted steam environments. design complies G2 ASTM standards studying zirconium its offers remote pressure monitoring during data collection. use exemplified by oxidation metallic exposure at 350 °C....