|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Electron Microscopy Characterization of the Fuel-cladding Interaction in Annular Fast Reactor MOX
||Fabiola Cappia, Alex Winston, Brandon Miller, Jeffery Aguiar, Boopathy Kombaiah, Fei Teng, Daniel Murray, Jason Harp
|On-Site Speaker (Planned)
Mixed Oxide (MOX) fuels for fast reactor are the reference fuel system for Sodium Fast Reactors (SFRs). In SFR MOX significant migration of fission products and fuel components occurs, resulting in fuel-cladding chemical interaction (FCCI). In this work, we present microscopy data focused on the FCCI layer in annular fast reactor MOX with HT-9 cladding at both medium and high burnup. In particular, the behavior of volatiles and the cladding components is studied. At intermediate burnup, accumulation of Cs, Te and I occurred in the outermost rim of the fuel pellet, where grain recrystallization has also been observed. The morphology and chemistry of the layer suggest a non-oxidative corrosion mechanism as principal cladding degradation phenomenon, with local onset of Cr oxidation within the nanocrystalline precipitates. At high burnup, the FCCI layer is composed mainly by Cs2MoO4. However, combinatorial analyses reveal that other non-stoichiometric phases are possible.