A5034023116- Nuclear Materials and Properties
- High-Temperature Coating Behaviors
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Nuclear materials and radiation effects
- Intermetallics and Advanced Alloy Properties
- Advanced ceramic materials synthesis
- Advanced materials and composites
- Ion-surface interactions and analysis
- Coal Combustion and Slurry Processing
- Aluminum Alloys Composites Properties
- High Temperature Alloys and Creep
- Numerical methods in engineering
- MXene and MAX Phase Materials
- Material Properties and Applications
- Metal Alloys Wear and Properties
- Aluminum Alloy Microstructure Properties
- Nuclear Physics and Applications
- Economic and Business Development Strategies
- Non-Destructive Testing Techniques
- Mechanical Behavior of Composites
- High-Velocity Impact and Material Behavior
- Materials Engineering and Processing
- Inorganic Chemistry and Materials
- Structural Health Monitoring Techniques
Westinghouse Electric (United States)
2008-2024
Westinghouse Electric (Japan)
2023
Mendel University in Brno
2023
University of Wisconsin–Madison
2008-2020
Sandia National Laboratories
2008
Two FeCrAl alloy coatings with different Cr and Al contents were deposited on Zr-alloy substrates via the cold spray deposition method to study efficacy of these improve accident tolerance fuel cladding in light water reactors (LWRs). First, tested a 400 °C steam autoclave for 72 h as an accelerated simulate normal LWR operating conditions. In tests, both resulted notable improvements oxidation resistance compared Zr-alloy, higher containing coating exhibiting thinner oxide layer. Both...
A novel fabrication method of oxide dispersion strengthened (ODS) steel cladding tubes for advanced fast reactors has been investigated using the cold spray powder-based materials deposition process. Cold spraying potential advantage rapidly fabricating ODS in comparison with conventional multi-step extrusion gas atomized spherical 14YWT (Fe-14%Cr, 3%W, 0.4%Ti, 0.2%Y, 0.01%O) powder was sprayed on a rotating cylindrical 6061-T6 aluminum mandrel nitrogen as propellant gas. The lacked oxygen...
Chromium (Cr)-coated Zircaloy fuel cladding has been considered a promising candidate materials system for accident tolerant fuels. In this work, two types of Cr coatings produced by cold sprayed (CS) and physical vapour deposited (PVD) methods were studied. particular, novel combination C-ring compression tests at room temperature (RT) 345°C in an inert gas environment real-time X-ray micro-computed tomography (XCT) imaging was adopted to investigate the failure processes. Before testing,...
The University of Wisconsin Ion Beam Laboratory (UW-IBL) has recently undergone significant infrastructure upgrades to facilitate graduate level research in irradiated materials phenomena and ion beam analysis. A National Electrostatics Corp. (NEC) Torodial Volume Source (TORVIS), the keystone upgrade for facility, can produce currents hydrogen ions helium up ∼200 μA ∼5 μA, respectively. Recent also include RBS analysis packages, end station developments irradiation relevant material...