
Wenzhong Zhou
Associate Professor
- Office: TBD
- Email: wenzhong.zhou@ucf.edu
- Phone: 407-823-2416
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- ResearchGate
BIOGRAPHY
Wenzhong Zhou is an associate professor in the Department of Mechanical and Aerospace Engineering at the University of Central Florida and a faculty member of the university’s Resilient, Intelligent and Sustainable Energy Systems Center, or RISES. Prior to joining UCF, he served as a principal engineer at Westinghouse Electric Company, an associate professor at Sun Yat-sen University, an assistant professor at the City University of Hong Kong, and a postdoctoral research associate at Los Alamos National Laboratory.
Zhou directs the M³ Nuclear Systems Laboratory (Multiphysics • Multiscale • Multiphase for Advanced Nuclear Energy), which focuses on the development of multiscale and multiphysics modeling and simulation methods for nuclear fuels and materials, reactor safety and thermal-hydraulics. His research supports both existing light water reactors and advanced nuclear energy systems, including small modular reactors (SMRs), microreactors, liquid metal reactors (LMRs), molten salt reactors (MSRs), and high-temperature gas-cooled reactors (HTGRs). Zhou has established a strong record of sponsored research as principal investigator and co-principal investigator on projects funded by government agencies, universities, industry and international collaborations.
His research has been published in leading journals across thermal sciences, materials, and nuclear engineering, including Nature Communications, Applied Thermal Engineering, and the International Journal of Heat and Mass Transfer, as well as prominent nuclear energy journals such as Nuclear Engineering and Design, Annals of Nuclear Energy, and Progress in Nuclear Energy. He has authored more than 60 peer-reviewed journal articles and over 50 conference papers, and his work has been widely cited by researchers in the fields of nuclear engineering, thermal sciences, and energy systems. His research contributions have been recognized in major reference works, including the Handbook of Materials Modeling and the Handbook of Generation IV Nuclear Reactors. He has also co-edited three scholarly books and serves as an associate editor for multiple journals. In addition, he has served as a track chair or co-chair for the International Conference on Nuclear Engineering (ICONE) for six consecutive years.
EDUCATION
- Ph.D. in Nuclear Engineering – Purdue University
- M.S. in Mechanical Engineering – Tianjin University
- B.S. in Mechanical Engineering – Tianjin University
RESEARCH
- Multiscale and multiphysics modeling, simulation methods, and code development for nuclear fuel and reactor applications
- Nuclear fuels and materials, including accident-tolerant fuels, high-burnup fuels, and high-assay low-enriched uranium (HALEU) fuels
- Multiphase flow, heat and mass transfer, and coupled transport phenomena
- Nuclear thermal-hydraulics, reactor safety, and severe accident analysis
- Advanced nuclear energy systems, including small modular reactors (SMRs), microreactors (MMRs), liquid metal reactors (LMRs), molten salt reactors (MSRs), and high-temperature gas-cooled reactors (HTGRs)
PUBLICATIONS
- Jingyu Guo, Shaojie Tan, Kai Wang, Songbai Cheng*, Wenzhong Zhou*, Development of a fission gas release and swelling model for sodium-cooled fast reactor fuels, Nuclear Engineering and Design, volume 418, March 2024, 112919.
- Xiaojing Li, Yu Ma*, Wenzhong Zhou* and Zhao Liu, Spin-polarized DFT calculations of elemental effects on hydrogen atom adsorption on FeCrAl (110) surface, Applied Surface Science, 581 (2022) 152273, https://doi.org/10.1016/j.apsusc.2021.152273
- Meng Yu, Libo Qian, Wenzhong Zhou*, Multiphysics Investigation on Coolant Thermohydraulic Conditions and Fuel Rod Behavior During a Loss-of-Coolant Accident, Frontiers in Energy Research, June 2021, Volume 9, Article 691813, doi: 10.3389/fenrg.2021.691813
- Shuai Ren, Wenzhong Zhou*, Numerical investigation of nucleate pool boiling outside a vertical tube under sub-atmospheric pressures, International Communications in Heat and Mass Transfer, 116 (2020) 104662.
- Jie Wei, Wei Zhou, Song Li, Pei Shen, Shuai Ren, Alice Hu, Wenzhong Zhou*, Modified Embedded Atom Method Potential for Modeling the Thermodynamic Properties of High Thermal Conductivity Beryllium Oxide, ACS Omega, 2019, 4, 6339−6346.
- Jie Wei, Song Li, Wei Zhou, Pei Shen, Shuai Ren, Alice Hu, Wenzhong Zhou*, First principles investigation of water adsorption on FeCrAl (110) surfaces, Applied Surface Science, 465 (2019) 259-266.
- Wei Zhou and Wenzhong Zhou*, Thermophysical and mechanical analyses of UO2-36.4 vol% BeO fuel pellets with Zircaloy, SiC, and FeCrAl claddings, Metals, 2018, 8(1), 65, pp. 1-14; doi: 10.3390/met8010065.
- Rong Liu, Wenzhong Zhou*, Andrew Prudil, and Paul K. Chan, Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties, Applied Thermal Engineering, 107 (2016) 86–100.
- George Westinghouse Signature Award, Nominee, Westinghouse Electric Company, 2026
- Westinghouse PowerUP Awards (Gold and Platinum), Westinghouse Electric Company, 2025–2026
- Certificates of Appreciation for Technical Leadership and Service as Track Chair/Co-Chair, International Conference on Nuclear Engineering (ICONE31–ICONE32), 2024–2025
- Student Poster Competition Award (as Supervisor), International Conference on Nuclear Engineering (ICONE26), 2018
- Recognition for Excellence in Scholarly Review, including Outstanding Reviewer and Certificates of Excellence in Reviewing for Progress in Nuclear Energy, and Elsevier Reviewer Badge in Nuclear Energy
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