| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
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| Symposium
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Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
Interfacial Microstructure Evolution in Al6061-Al6061 HIP Bonded Samples for Cladding Applications on U-10Mo Monolithic Fuel |
| Author(s) |
Rajib Kalsar, Miao Song, Cody Miller, Nicole Overman, Kenneth Johnson, Timothy Roosendaal, Curt Lavender, Vineet Joshi |
| On-Site Speaker (Planned) |
Rajib Kalsar |
| Abstract Scope |
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. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Aluminum, Nuclear Materials, Mechanical Properties |