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Zeyun Wu, Ph.D. - VCU College of Engineering. BioTech One, Room 1070C, Richmond, VA, US

Zeyun Wu, Ph.D. Zeyun Wu, Ph.D.

Assistant Professor, Department of Mechanical and Nuclear Engineering | VCU College of Engineering

BioTech One, Room 1070C, Richmond, VA, UNITED STATES

Nuclear reactor physics, reactor core design, computational methods for reactor analysis, sensitivity and uncertainty analysis

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Biography

Dr. 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). 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 from Tsinghua University at Beijing China and Ph.D. degree from Texas A&M University, both in nuclear engineering. Dr. Wu have had post-doc training at North Carolina State University and Purdue University, respectively. His research interests encompass reactor physics, reactor core design and analysis, computational methods on neutron transport and uncertainty and sensitivity analysis in nuclear applications.

Areas of Expertise (4)

Reactor Physics

Reactor core design and analysis

Computational method for neutron transport

Uncertainty and sensitivity analysis

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 (3)

  • Member, American Nuclear Society (ANS)
  • Member, Program Committee, Reactor Physics Division, ANS
  • Member, Publication Steering Committee, ANS

Courses (2)

EGMN 352 - Nuclear Reactor Theory

Introduces 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.

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.