Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Monolithic U-10Mo alloy fuel plates with Al-6061 cladding are being developed for use in research and test reactors as low enrichment fuel (1 μm) are distributed evenly in U-Mo and interlink of these bubbles is evident. The average size of subdivided grains at this fission density appears similar to...

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Bibliographic Details
Published in:Journal of nuclear materials 2017-08, Vol.492 (C), p.195-203
Main Authors: Gan, J., Miller, B.D., Keiser, D.D., Jue, J.F., Madden, J.W., Robinson, A.B., Ozaltun, H., Moore, G., Meyer, M.K.
Format: Article
Language:English
Subjects:
Aluminum base alloys
Bearing strength
Bubbles
Cladding
Cold rolling
Density
Diffusion
Diffusion barriers
Diffusion plating
Dispersion
End of life
Enriched fuel reactors
Enrichment
Fission
Fission density
Fission gas bubble
Foils
Hot rolling
Irradiated microstructure
Irradiated U-Mo fuel
Irradiation
MATERIALS SCIENCE
Mathematical analysis
Microstructure
Molybdenum
Nuclear fission
NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Nuclear fuels
Plates
Radiation
Reactors
TEM Characterization
Uranium
Uranium base alloys
Zirconium
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Summary:Monolithic U-10Mo alloy fuel plates with Al-6061 cladding are being developed for use in research and test reactors as low enrichment fuel (1 μm) are distributed evenly in U-Mo and interlink of these bubbles is evident. The average size of subdivided grains at this fission density appears similar to that at 5.2E+21 fissions/cm3. The measured average Mo and Zr content in the fuel matrix is ∼30 at% and ∼7 at%, respectively, in general agreement with the calculated Mo and Zr from fission density.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2017.05.035