Brandon Miller
Materials Science · Purdue University West Lafayette
Publications
109
Citations
1,715
Est. group size
~1
Recurring co-author estimate
Active years
26
Publishing since 2001
Brandon Miller's work focuses on nuclear fuel materials, particularly how uranium-molybdenum (U-Mo) and uranium-plutonium-zirconium (U-Pu-Zr) fuels change structurally and chemically when exposed to radiation in nuclear reactors. This involves using advanced microscopy and imaging techniques to study porosity, swelling, gas bubble formation, and interactions between fuel and cladding materials at high burnup (a measure of how much energy has been extracted from nuclear fuel). One unrelated dataset publication on black walnut syrup flavor also appears in the record.
Publication output has gradually declined over the last decade, dropping from around 10 papers per year in 2017 to roughly 2-4 per year in recent years.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Data from: Consumer Acceptability and Flavor Attributes of Black Walnut Syrup: Tapping into a Climate-resilient and Profitable Alternative to Traditional Syrups
Ag Data Commons · 2026
- Data from: Consumer Acceptability and Flavor Attributes of Black Walnut Syrup: Tapping into a Climate-resilient and Profitable Alternative to Traditional Syrups
Ag Data Commons · 2026
- Porosity, Swelling, and Composition Evolution in High-Burnup Monolithic U-Mo Fuel
SSRN Electronic Journal · 2025
- Porosity, swelling, and composition evolution in high-burnup monolithic U-Mo fuel
Journal of Nuclear Materials · 2025
- Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils
Journal of Nuclear Materials · 2024
- Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel
Journal of Nuclear Materials · 2024
- Atom probe tomography of segregation at grain boundaries and gas bubbles in neutron irradiated U-10 wt% Mo fuel
Materials Letters · 2024
- Summary Report on Ion Irradiation Study of Ceramic Coating on Suppressing FCCI
2024
- Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel
Nuclear Materials and Energy · 2023
- Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels
Journal of Nuclear Materials · 2023
- Evidence of Xe-incorporation in the bubble superlattice in irradiated U-Mo fuel
Journal of Nuclear Materials · 2023
- Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils
Nuclear Materials and Energy · 2023
- Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
Journal of Nuclear Materials · 2023
- Status Report on Ion Irradiation Study of Ceramic Coating in Suppressing Fuel/Cladding Chemical Interaction
2023
- Signed, Your Friendly Columnist
2023
- Journal of Nuclear Materials×27
- Microscopy and Microanalysis×6
- Nuclear Materials and Energy×2
- Micron×2
- Ag Data Commons×2
- Md Ali Muntaha
Materials Science · Purdue University West Lafayette
- Jian Gan
Materials Science · Purdue University West Lafayette
- Maria A. Okuniewski
Materials Science · Purdue University West Lafayette
- Logan Joyce
Materials Science · Purdue University West Lafayette
- Sanjoy Mazumder
Materials Science · Purdue University West Lafayette
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 20, 2026.
Claim or correct this profile