Dr. Lingfeng He
Distinguished Staff Scientist and High-Resolution Materials Characterization (HRMC) Group Lead
Idaho National Laboratory

Abstract

Ceramic nuclear fuels have been widely used in light water reactors or proposed as candidates for advanced reactors. The thermal conductivity of ceramic nuclear fuels is closely related to energy conversion efficiency as well as reactor safety margins. Understanding the mechanisms that cause the degradation of thermal conductivity in a high radiation environment is important for the design and development of new high-burnup fuels. In this work, defects and/or phase evolution in UO₂, ThO₂ and UN under irradiation are studied by a combination of ion irradiation, advanced characterization, and modeling.  In addition, the relationship between defects and thermal transport is probed on ion-irradiated oxide fuels.

Biography

Dr. Lingfeng He is a Distinguished Staff Scientist and High-Resolution Materials Characterization Group Lead in Characterization and Advanced PIE Division at Idaho National Laboratory (INL). He is the Deputy Director of the Center for Thermal Energy Transport under Irradiation (TETI), an Energy Frontier Research Center funded by DOE’s Office of Science.  Dr. He received a Ph.D. degree in Materials Science at the Chinese Academy of Sciences in 2009. ​ He worked as a Post-doctoral Research Associate and Assistant Scientist at Nagaoka University of Technology in Japan and the University of Wisconsin-Madison before joined INL in 2014. He is the recipient of INL Laboratory Director’s 2020 Exceptional Scientific Achievement Award.

Thursday, April 21. 2022
4:00 pm seminar

Hybrid Option  (Speaker is in person)

zoom (link upon request)
or
Room 1202 Burlington Labs