W. J. Williams
Earth and Planetary Sciences · Purdue University West Lafayette
Publications
138
Citations
1,853
Est. group size
~1
Recurring co-author estimate
Active years
61
Publishing since 1965
W. J. Williams works on nuclear fuel materials, particularly uranium-based alloys like U-Mo, U-Zr, and U3Si2 used in research and test reactors. Their work involves examining how these fuels change structurally when irradiated (exposed to radiation), using techniques such as electron microscopy, X-ray diffraction, and neutron imaging to understand swelling, phase changes, and fabrication methods. This research supports efforts to qualify and improve nuclear fuel designs for safety and performance.
Publication output has been steady but modest over the last decade, fluctuating between one and five papers per year without a clear long-term increase or decline.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- A critical review of the history of fabricating monolithic U-Mo fuel plates
Journal of Nuclear Materials · 2025
- A Critical Review on the History of Fabricating Monolithic U-Mo Fuel Plates
2024
- Microstructure and phase evolution in the U-10Zr fuel investigated by in situ TEM heating experiments.
Journal of Nuclear Materials · 2023
- Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction
Journal of Nuclear Materials · 2023
- The formation mechanism of the Zr rind in U-Zr fuels
Journal of Nuclear Materials · 2022
- Post-irradiation examination of legacy high burnup fuel to support safety testing
2021
- U-50Zr Microstructure and Property Assessment for LWR Applications
2021
- Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm
Nuclear Technology · 2021
- Swelling of U-Mo Monolithic Fuel: Developing a Predictive Swelling Correlation under Research Reactor Conditions
Journal of Nuclear Materials · 2020
- The use of U3Si2/Al dispersion fuel for high power research reactors
Journal of Nuclear Materials · 2019
- Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment
JOM · 2017
- Conversion from Film to Image Plates for Transfer Method Neutron Radiography of Nuclear Fuel
Physics Procedia · 2017
- Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment
Journal of Nuclear Materials · 2017
- Determination of optimal imaging parameters for the reconstruction of a nuclear fuel assembly using limited angle neutron tomography
Journal of Instrumentation · 2016
- Journal of Nuclear Materials×12
- JOM×2
- Annals of Nuclear Energy×1
- Physics Procedia×1
- Nuclear Technology×1
- Michael W. Hess
Earth and Planetary Sciences · Indiana University
- Lan Luan
Earth and Planetary Sciences · Indiana University
- Brian H. Stirm
Environmental Science · Purdue University West Lafayette
- Mengyun Li
Earth and Planetary Sciences · The Ohio State University
- Daniel M. Murphy
Earth and Planetary Sciences · 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