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Zeyun Wu, Ph.D. - VCU College of Engineering. Richmond, VA, US

Zeyun Wu, Ph.D.

Associate Professor, Department of Mechanical and Nuclear Engineering | College of Engineering


Reactor physics, computational methods, sensitivity and uncertainty analysis, advanced data analytics, machine learning



Dr. Wu joined the Department of Mechanical and Nuclear Engineering at Virginia Commonwealth University (VCU) in August 2017 and directs the Computation Applied Reactor Physics Laboratory (CARPL). Prior to VCU, Dr. Wu worked at National Institute of Standards and Technology (NIST) in charge of a replacement research reactor design project. Dr. Wu received his B.S. degree in Engineering Physics from Tsinghua University at Beijing China and Ph.D. degree in Nuclear Engineering from Texas A&M University at College Station Texas. Dr. Wu's research interests encompass reactor physics, multiphysics based reactor design and analysis, computational methods on neutron transport and uncertainty and sensitivity analysis in nuclear applications, machine learning and data analytics.

Areas of Expertise (5)

Reactor Physics

Reactor core design and analysis

Computational method for neutron transport

Uncertainty and sensitivity analysis

Advanced data analytics

Education (4)

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 (4)

  • 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 (2)

In search of lost data

College of Engineering, VCU  online


Nuclear engineering faculty member recreates missing data from watershed 1960s reactor experiments

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Young Former Student Award 2019

Texas A&M University  online


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.

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Research Grants (2)

Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation

Department of Energy - NEUP $320,000


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.

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Identifying and Prioritizing Sources of Uncertainty in External Hazard Probabilistic Risk Assessment

Department of Energy - NEUP $150,000


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.

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Courses (2)

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.