A5045144991- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Radioactive element chemistry and processing
- Fusion materials and technologies
- Nuclear materials and radiation effects
- Molten salt chemistry and electrochemical processes
- Superconducting Materials and Applications
- Intermetallics and Advanced Alloy Properties
- Rare-earth and actinide compounds
- Advanced ceramic materials synthesis
- Nuclear and radioactivity studies
- Particle accelerators and beam dynamics
- Physics of Superconductivity and Magnetism
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Material Properties and Applications
- Advanced materials and composites
- High-Temperature Coating Behaviors
- High Temperature Alloys and Creep
- Particle Accelerators and Free-Electron Lasers
- Aluminum Alloys Composites Properties
- Real-time simulation and control systems
- Catalysis and Oxidation Reactions
- Radiation Effects and Dosimetry
- Subcritical and Supercritical Water Processes
The University of Texas at San Antonio
2017-2024
Los Alamos National Laboratory
2012-2020
Los Alamos Medical Center
2020
University of Akron
2020
Texas A&M University
2011-2015
Mitchell Institute
2013
Marshall Space Flight Center
2009
As part of Accident Tolerant Fuel initiative for light water reactors, uranium silicide and silicide-nitride are being considered as fuels that can be combined with a more robust cladding such ferritic (FeCrAl) alloy. Although these materials have been studied in the past, uncertainties remain concerning fundamental behaviour systems. In this study, four compositions between U3Si5 USi2 were fabricated by arc-melting. Additionally, an effort to understand UN–U3Si2 fuel system, unidentified...
Molybdenum disilicide (MoSi 2 ) has well documented oxidation resistance at high temperature (T > 1273 K) in dry O containing atmospheres due to the formation of a passive SiO surface layer. However, its behavior under where water vapor is dominant species received far less attention. Oxidation testing MoSi was performed temperatures ranging from 670–1498 K both 75% and synthetic air (Ar‐O , 80%–20%) atmospheres. Here thermogravimetric microscopy data describing these phenomena are...
Changes in chemical speciation of uranium oxides following storage under varied conditions temperature and relative humidity are valuable for characterizing material provenance. In this study, subsamples high purity α-UO3 were stored four sets controlled over several years, then measured periodically speciation. Powder X-ray diffraction (XRD) analysis extended absorption fine structure spectroscopy confirm hydration to a schoepite-like end product each the conditions, but species formed...
Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation Peter McIntyre, Saeed Assadi, Karie Badgley, William Baker, Justin Comeaux, James Gerity, Joshua Kellams, Al McInturff, Nathaniel Pogue, Supathorn Phongikaroon, Akhdiyor Sattarov, Michael Simpson, Elizabeth Sooby, Pavel Tsvetkov; Accelerator-driven subcritical fission in molten salt core: Closing the nuclear...
Abstract The high‐temperature oxidation of additively manufactured and chemically vapor infiltrated (3D‐printed SiC) has been compared to chemical deposited (CVD) SiC. 100‐h isothermal exposures were conducted at 1425° 1300°C 1 atm under both dry air steam environments. A SiC reaction tube was utilized reduce silica volatility. After 1300°C, on the 3D‐printed surface, which intrinsically rougher than CVD scales 70%–90% thicker convex regions concave/flat regions. In regions, large cracks...