Apr 9, 2025
11:00am - 11:15am
Summit, Level 3, Room 339
Allison Probert1,Mitchell Mika1,Cade Finney1,Casey McKinney2,Timothy Lach2,Jason Harp2,Assel Aitkaliyeva1,3
University of Florida1,Oak Ridge National Laboratory2,Idaho National Laboratory3
Allison Probert1,Mitchell Mika1,Cade Finney1,Casey McKinney2,Timothy Lach2,Jason Harp2,Assel Aitkaliyeva1,3
University of Florida1,Oak Ridge National Laboratory2,Idaho National Laboratory3
A comprehensive understanding of the fuel-cladding chemical interaction (FCCI) in high burnup UO
2 is needed to ensure cladding integrity and predict fuel performance beyond the current burnups of commercial nuclear fuel. This study investigates the FCCI and high burnup structure (HBS) regions in a discharged light water reactor (LWR) UO
2 fuel pellet irradiated to a burnup of approximately 73 MWd/kgU. A combination of analytical techniques—focused ion beam (FIB) tomography, energy dispersive spectroscopy (EDS), transmission Kikuchi diffraction (tKD), and transmission electron microscopy (TEM)—was employed to examine the microstructural and chemical evolution in these regions. The 3D structural and compositional reconstructions of the FCCI reveal critical changes in material microstructure and behavior, including porosity, fuel cracking, and chemical alterations. Simultaneously, lower-length scale analyses provide detailed insights into grain character, fission gas precipitation, and phase transformations. These findings will inform and validate mechanistic meso-scale material models, such as those used in MARMOT, to accurately predict key thermomechanical properties and assess fuel and cladding performance at higher burnups.