Dr. Shaoqiang Guo is a Research Scientist in the Department of Mechanical Engineering and the Nuclear Materials and Fuel Cycle Center at Virginia Tech (VT). Before joining VT in December 2016, he had been a Post Doctoral Researcher for two years in Prof. Jinsuo Zhang’s group at the Ohio State University (OSU). Prior to OSU, he did two-year research at the Institute for Corrosion and Multiphase Technology at Ohio University. He received both his B.E. and Ph.D. in materials science and engineering from University of Science and Technology Beijing. He has years of research experience on the materials corrosion in aqueous and molten salt media, electrochemistry, corrosion control and modeling. His research interests include structural materials corrosion and prevention, molten salt coolant, and application of electrochemical separation techniques in the advanced molten salt reactors and the pyroprocessing of spent nuclear fuel.
Ryan Chesser is a Ph.D. student in Nuclear Engineering. He graduated from The Ohio State University in 2015 with a B.S. in Chemical Engineering, and a minor in Nuclear Engineering. His Ph.D. work is with Dr. Jinsuo Zhang as part of the Nuclear Materials and Fuel Cycle Center at Virginia Tech.
Ryan’s research focuses on the application of electrochemical techniques for studying molten fluoride salt systems related to the Fluoride salt-cooled High-temperature Reactor (FHR). His current project proposes to generate missing electrochemical data for common fission products and other contaminants in molten fluoride salt. With this data, he will implement redox control and develop a cleanup system for removing impurities from the primary coolant loop of the FHR to reduce risk of high-level radioactivity and corrosion.
Amanda Sue Wen Leong
Amanda graduated with a B.S. in Mechanical Engineering in 2017 from The Ohio State University together with a minor in Nuclear Engineering. She currently is pursuing her Ph.D. in Mechanical Engineering at Virginia Tech. Her research focuses on corrosion studies on multi-metallic layer composite materials. Her interests are in developing corrosion mechanisms analysis methods and, reciprocally, to use these approaches to better understand the corrosion mechanisms, in hope to assuage concerns on corrosion risks in nuclear applications.
Weiqian Zhuo has been a member of NMFC since 2017. He is pursuing his Ph.D. by conducting the researches that focused on advanced nuclear fuel materials. Currently he is working on a nuclear metallic fuel project. His research involves experiment and simulation. For experiment, he focuses on evaluation and optimization of the thermodynamic properties and phase diagram of a ternary system by using DSC, SEM, XRD, etc. For simulation, he is using MOOSE to study the liquid-like Ln transportation behavior and the phase field model in metallic fuel.
He completed his Bachelor’s and Master’s Degree in Nuclear Engineering in 2013 and 2016 at North China Electric Power University.
Virginia Polytechnic Institute and State University Aug. 2017 –
·Major in Nuclear Program
Xi’an Jiaotong University Sept. 2008 – Jul. 2012
·Bachelor of Engineering in Nuclear Engineering and Nuclear Technology
Hainan Yiling Engineering Co., Ltd Jan, 2015 – May, 2017
A subsidiary of Shenzhen Yiling Engineering Corporation
Engineering Design Dept.
·Project designer in charge of engineering design
Hainan Nuclear Power Co., Ltd Jul, 2012 – Jan, 2015
A subsidiary of China National Nuclear Corporation
Instrument Control Dept.
·Assistant engineer in charge of KSN, KME, KDO system
Brendan D’Souza received his Masters degree in Nuclear Engineering from Missouri University of Science and Technology, in 2015, and Bachelors in Mechanical Engineering from Mumbai University in 2010. He is currently a PhD student working under Dr. Jinsuo Zhang at the Center for Nuclear Materials and Fuel Cycle Research at Virginia Tech.
His research focuses on the studying the flow induced corrosion for materials in molten chloride salt system for high temperature Molten Salt Reactors (MSRs). The research is primarily focused on developing a high temperature isothermal / non-isothermal flow loop replicating the MSR conditions in order to study the kinetic behavior of material corrosion and its compatibility in molten chloride salt system. His previous work also involved studying the Al corrosion behavior in borated aqueous based solution under varying LOCA conditions in light water reactors.
B.S. University of South China, 2006-2010
M.S. Xiamen University, 2010-2013
Research Associate Nuclear Power Institute of China, 2013-present
Visiting scholar Virginia Tech, 2017-present
Advanced nuclear metal fuels and accident tolerant fuels development
Advanced cladding materials development
Nuclear materials degradation
Manufacturing questions of fuel plates