Zeyun Wu, Ph.D.
Associate Professor, Department of Mechanical and Nuclear Engineering
- Richmond VA UNITED STATES
- Engineering East Hall E2236
- Mechanical and Nuclear Engineering
Reactor physics, computational methods, sensitivity and uncertainty analysis, advanced data analytics, machine learning
Social
Biography
Areas of Expertise
Education
Texas A&M University
Ph.D.
Nuclear Engineering
2010
Texas A&M University
M.E.
Nuclear Engineering
2005
Tsinghua University, Beijing, China
M.S.E.
Engineering Physics
2001
Tsinghua University, Beijing, China
B.S.
Engineering Physics
1999
Affiliations
- Member, American Nuclear Society (ANS)
- Member, Publication Steering Committee, ANS
- Member, Executive Committee, Reactor Physics Division, ANS
- Member, Executive Committee, Mathematics and Computation Division, ANS
Media Appearances
In search of lost data
College of Engineering, VCU online
2021-07-26
Nuclear engineering faculty member recreates missing data from watershed 1960s reactor experiments
Young Former Student Award 2019
Texas A&M University online
2019-10-01
The 2019 Young Former Student Award winner was Dr. Zeyun Wu. Wu is an assistant professor in the Department of Mechanical and Nuclear Engineering at Virginia Commonwealth University (VCU) and directs the Computation Applied Reactor Physics Laboratory (CARPL) at VCU. Wu received his Ph.D. in nuclear engineering at Texas A&M University with a research focus on reactor physics and computational methods on neutron transport.
Research Grants
Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation
Department of Energy - NEUP
2021-10-01
Researchers will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook.
Identifying and Prioritizing Sources of Uncertainty in External Hazard Probabilistic Risk Assessment
Department of Energy - NEUP
2020-10-01
Researchers will develop a method for identifying and prioritizing sources of uncertainty in external hazard probabilistic risk assessment for nuclear power plants, with particular emphasis on uncertainties associated with hazard characterization. External flooding wil be utilized as the demonstration hazard during this project, while a common taxonomy for communicating uncertainties across a broad range of external hazards will be created.
Courses
EGMN 303 - Thermal System Design
Introduce fundamentals of heat transfer, thermodynamics and fluid mechanics, as well as basics for system simulations and optimizations. Students are required to apply these fundamentals to the thermal analysis, design, selection and application of energy conversion systems. This is a project based course.
EGMN 352 - Nuclear Reactor Theory
Introduce fundamental properties of the neutron, the reactions induced by neutrons, nuclear fission, the slowing down of neutrons in infinite and finite media, diffusion theory, the 1-group or 2-group approximation, point kinetics, and fission-product poisoning. Provides students with the nuclear reactor theory foundation necessary for reactor design and reactor analysis problems.