Next generation Westinghouse nuclear power plants and their thermal fluids research and development
Westinghouse Electric Company
Abstract
Westinghouse continues developing the next generation advanced nuclear power plants, which will provide clean and reliable electricity together with diverse applications. The technology of these plants ranges from the mature light water reactor to innovative Generation-IV liquid metal reactors. The design and key technologies of AP300 small modular reactor, eVinci microreactor and lead-cooled fast reactor will be introduced. The research and development related to thermal fluids of these reactors will be presented with a focus on the experimental facilities and analysis for the liquid lead cooled fast reactor.
About the speaker
Dr. Jun Liao earned a B.S. in Power Engineering at the Huazhong University of Science and Technology (1994), M.S. in Mechanical Engineering at Xi’an Jiaotong University (1997), and Ph.D. in Aerospace Engineering at the University of Florida (2005). He is a Fellow Engineer in the Advanced Reactor Development group at Westinghouse Electric Company. Dr. Liao is an expert in the thermal hydraulics of nuclear reactors and the development of modeling and simulation computer codes. In Westinghouse, Dr. Liao’s responsibilities include developing safety analysis computer codes and methodologies for both light water and non-light water reactors. He developed and licensed the FULL SPECTRUM LOCA methodology for pressurized water reactor safety analysis. He played an important role in the development of Westinghouse’s advanced nuclear power plants, including the AP1000, Westinghouse SMR/AP300, Westinghouse Lead Fast Reactor, and eVinci microreactor. Dr. Liao led the modeling and simulation development effort for the eVinci microreactor and is the safety analysis lead of the Lead-cooled Fast Reactor project. He has published over 100 journal articles and conference papers. Dr. Liao is a member of the American Nuclear Society (ANS) and American Society of Mechanical Engineers (ASME) and serves in three committees of ANS and ASME. He is an adjunct faculty in University of Pittsburgh and an associate editor of Journal of Nuclear Engineering and Radiation Science (ASME).
