Characterization of phases formed between U-Pu-Mo alloys and Fe-12Cr cladding
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-21.7Pu-4.3Mo and U-24.8Pu-14.6Mo (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, Fe2U, FeUCr, and Fe2Pu. Phases formed at the end of the FCCI layer in the U-21.7Pu-4.3Mo alloy included FeUCr, Fe2U, and Cr2FeO4 while in the U-24.8Pu-14.6Mo alloy; the phases were consistent with Cr0.49Fe0.51, Cr0.8Fe0.2, and FeUCr.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- DE-AC07-05ID14517
- OSTI ID:
- 1184720
- Report Number(s):
- INL/JOU-15-34264
- Journal Information:
- Journal of Nuclear Materials, Vol. 464
- Country of Publication:
- United States
- Language:
- English
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