Rhines Hall, Room 125
549 Gale Lemerand Drive
Gainesville, FL 32611
Please join the Nuclear Engineering Program for refreshments and a discussion lead by Dr. Kevin Field of Oak Ridge National Laboratory.
“Current Light Water Reactor (LWR) designs incorporate a half a century old fuel-cladding technology prone to severe accidents such as the one recently observed in 2011 at the Fukushima Daiichi nuclear power plant. Effective materials design for fuel cladding and fuel assemblies can lead to enhanced safety during off-normal conditions in LWRs without significantly impacting normal operating conditions. The use of targeted materials design has been demonstrated for the iron-chromium-aluminum (FeCrAl) alloy class over the past six years resulting in a new cladding product promised to increase safety in the current generation of LWRs. Included in this discussion will be a high-level overview of the alloy design efforts and detailed discussion on the impact of radiation effects on the final composition and microstructure used for lead-test rods within a commercially operating LWR. In addition, new computational and experimental tools which can greatly increase the rate of new alloy production will be discussed. The discussion will conclude on the future outlook and directions for the evolution of FeCrAl alloys for nuclear power applications.”
Nuclear Engineering Program