Article ID Journal Published Year Pages File Type
7965174 Journal of Nuclear Materials 2015 27 Pages PDF
Abstract
Exposure to high temperatures and irradiation can lead to interaction between fuel and cladding constituents, inter-diffusion, and formation of brittle or low-melting phases. Therefore, understanding of fuel-cladding interaction (FCCI) is critical for evaluation of fuel performance in a reactor environment. In this contribution, phases formed between U-22Pu-4Mo and U-25Pu-15Mo (in wt%) fuel alloys and Fe-12Cr cladding were characterized using scanning and transmission electron microscopy (SEM/TEM) techniques. Phases formed within FCCI layers in both alloys were identified by implementing selective area diffraction pattern analysis as Cr0.3Mo0.7 (Im-3m), Fe2U (Fd-3m), UCrFe (Fd-3m), and Fe2Pu (Fd-3m). Phases formed at the end of the FCCI layer in the U-22Pu-4Mo alloy included UCrFe (Fd-3m), Fe2U (Fd-3m), and Cr2FeO4 (Fd-3m) while in the U-25Pu-15Mo alloy the phases were consistent with Cr0.49Fe0.51 (P42/mnm), Cr0.8Fe0.2 (Im-3m), and UCrFe (Fd-3m).
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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