Seminar: Recent Advancements in Understanding of Nuclear Fuel Performance

Dr. Marat Khafizov, The Ohio State University

All dates for this event occur in the past.

E141 Scott Lab
201 W. 19th Ave.
Columbus, OH 43210
United States

Abstract

Safety analysis of reactor operation relies on fuel performance codes that model thermo-mechanical state of the nuclear fuel.  Standard fuel performance codes are based on the experimental data that relate thermal and mechanical properties of fuel and cladding materials to the fuel burnup.  Historically, fuel performance codes were used for predicting the centerline temperature and fission gas release.  Recent advancement allow to model more sophisticated phenomena, such as cladding failure due to fuel pellet mechanical interactions or missing pellet surface.  However it is not clear if these phenomenological codes can adequately describe the state of the system during the scenarios that are beyond normal operation.  In order to improve predictive capability, current efforts are in the development of codes that implement science based understanding of radiation damage evolution and its effect on physical properties.  In this presentation, recent experimental and computational efforts that support the development of advanced performance codes will be reviewed.

About the Speaker

Dr. Marat Khafizov is an assistant professor in the Department of Mechanical and Aerospace Engineering at The Ohio State University.  He received his Ph.D. in Physics from the University of Rochester.  His current research interests are in the understanding of physical properties of materials developed for sustainable energy applications.  Prior to joining OSU, he was a research scientist at Idaho National Laboratory where he conducted research aimed at understanding of thermo-physical properties of nuclear fuel materials.  He currently directs the Laboratory for Thermal Properties of Materials for Extreme Environments.

Hosted by Professor Xiaodong Sun