Wenzhong Zhou
Materials Science · Purdue University West Lafayette
Publications
127
Citations
3,045
Est. group size
—
Recurring co-author estimate
Active years
37
Publishing since 1990
Wenzhong Zhou's research focuses on nuclear fuel materials and reactor engineering, particularly how nuclear fuels behave under the extreme conditions inside reactors, including fission gas release, swelling, and thermo-mechanical performance. The work spans computational modeling (multiphysics simulations, finite element methods, and atomic-scale calculations) as well as experimental studies of material properties like corrosion resistance and irradiation effects, applied to fast reactors, light water reactors, and particle accelerator components.
Publication output has fluctuated over the past decade with a peak around 2018 and 2021, but has notably declined in the most recent years (2024-2026).
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Reconfiguring source-sink boundary conditions in immiscible displacement: Fractal kinetics and synergistic mechanisms in fractured networks
Advances in Water Resources · 2026
- Modeling Fuel Behavior in Liquid Metal Fast Reactors: A Multiphysics Approach with Jog Formation Analysis
SSRN Electronic Journal · 2025
- Preliminary Design of CSNS-II LINAC SRF LLRF based on C-ADS Injector I
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment · 2024
- Development of a fission gas release and swelling model for sodium-cooled fast reactor fuels
Nuclear Engineering and Design · 2024
- FEM (finite element method) thermal modeling and thermal hydraulic performance of an enhanced thermal conductivity UO<sub>2</sub>/BeO composite fuel
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2024
- The elemental effects on the H2 dissociative adsorption on FeCrAl (110) surface
International Journal of Hydrogen Energy · 2023
- The elemental weakening & aggregation effect on the hydrogen adsorption on FeCrAl (110) surface
Surfaces and Interfaces · 2023
- Alkaline corrosion resistance of slag‐free self‐shielded titanium‐added metal‐cored welding overlay
Materialwissenschaft und Werkstofftechnik · 2023
- Research on Bolt Support Technology in Soft Coal Seam Roadway
World Journal of Engineering and Technology · 2023
- Extended Development of a Fission Gas Release Behavior Model Inside Spherical Fuel Grains for LWR Reactors
Applied Sciences · 2023
- FISSION GAS RELEASE BEHAVIOR MODELING INSIDE SPHERICAL FUEL GRAINS
The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2023
- MULTIPHYSICS FISSION GAS RELEASE AND SWELLING BEHAVIOR FOR URANIUM-PLUTONIUM MIXED OXIDE FUELS IN A LEAD-COOLED FAST REACTOR
The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2023
- Deformation dynamics of a neutron-irradiated aluminum alloy: An in situ synchrotron tomography study
Acta Materialia · 2022
- Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments
Frontiers in Energy Research · 2022
- Multiphysics thermo-mechanical behavior modeling for annular uranium-plutonium mixed oxide fuels in a lead-cooled fast reactor
Frontiers in Energy Research · 2022
- Frontiers in Energy Research×9
- Annals of Nuclear Energy×6
- Nuclear Engineering and Design×3
- Transactions of the American Nuclear Society×3
- Applied Surface Science×2
- Ketan Ajay
Materials Science · Purdue University West Lafayette
- Md Ali Muntaha
Materials Science · Purdue University West Lafayette
- Brandon Miller
Materials Science · Purdue University West Lafayette
- Sanjoy Mazumder
Materials Science · Purdue University West Lafayette
- Logan Joyce
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