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Ke Shen is a Professor in the College of Materials Science and Engineering at Hunan University, China. He received his Bachelor's degree in Materials Science and Engineering from Tsinghua University in 2007 and completed his Ph.D. at the same University in 2013, focusing on nuclear-grade graphite research. Then, he conducted postdoctoral research at the Institute of Nuclear and New Energy Technology (INET), Tsinghua University, working on fuel elements for high-temperature gas-cooled reactors (HTRs).
He also spent a year as a visiting scholar at the University of California, Berkeley, where he conducted research on the thermal properties of graphite. In 2017, he joined the College of Materials Science and Engineering at Hunan University and was promoted to Full Professor in 2021.
His research interests include: The Physics and Chemistry of Carbon; High-Purity Carbon Materials; Preparation Technology of Artificial Graphite and Isostatic Graphite; Structural Characterization and Performance Evaluation of Nuclear-Grade Graphite for High-Temperature Gas-Cooled Reactors; Theory and Application of Other Carbon Materials. He is currently leading 4 General Programs and 1 Youth Program of the National Natural Science Foundation of China, as well as several research projects for Sinopec and CNNC. He has published over 50 research papers in journals such as Advanced Materials, Advanced Functional Materials, Carbon, and Journal of Nuclear Materials. He has received the First Prize of Science and Technology Award (Invention Category) from the China Non-Metallic Minerals Industry Association (ranked first) and the Best Paper Award at the 29th International Nuclear Engineering Conference.
Ph.D., Materials Science and Engineering, Tsinghua University, China, 2007–2013
B.E., Materials Science and Engineering, Tsinghua University, China, 2003–2007
High-Purity Carbon Materials
The Physics and Chemistry of Carbon
Theory and Application of Other Carbon Materials
Preparation Technology of Artificial Graphite and Isostatic Graphite
Structural Characterization and Performance Evaluation of Nuclear-Grade Graphite for HTGR