|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Interfacial microstructure evolution in Al6061-Al6061 HIP bonded samples for cladding applications on U-10Mo monolithic fuel
||Rajib Kalsar, Miao Song, Cody Miller, Nicole Overman, Kenneth Johnson, Timothy Roosendaal, Curt Lavender, Vineet Joshi
|On-Site Speaker (Planned)
Low-enriched uranium (LEU) alloyed with 10 wt% molybdenum (U-10Mo) has been identified as a promising alternative to high-enriched uranium (HEU) for the United States High Performance Research Reactors (USHPRR). The nominal configuration of the U-10Mo plate-type fuel is a metallic U-10Mo fuel foil, the thickness of which varies from 0.6 mm (0.025") to 0.2 mm (0.0085") depending on the reactor; a 25 μm thick Zr interlayer–diffusion barrier on either side, and an outer cladding of 6061 aluminum. The aluminum is clad on the co-rolled fuel using the HIP process. The impact of different HIP parameters on microstructure as well as bond strength was investigated. Interface microstructures were characterized using SEM, SEM-EBSD and TEM to quantify the oxide layer thickness, Mg2Si precipitate fraction and recrystallization across the interface. A correlation between interface microstructure and bond strength was also established.
||Aluminum, Nuclear Materials, Mechanical Properties