Microstructural Development in Irradiated U-7Mo/6061 Al Alloy Matrix Dispersion Fuel
A U-7Mo alloy/6061 Al alloy matrix dispersion fuel plate was irradiated in the Advanced Test Reactor and then destructively examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructures of as-fabricated dispersion fuel to identify changes that occurred during irradiation. The interaction layers that formed on the surface of the fuel U-7Mo particles during fuel fabrication exhibited stable irradiation performance as a result of the ~0.88 wt% Si present in the fuel meat matrix. During irradiation, the interaction layers changed very little in thickness and composition. The overall irradiation performance of the fuel plate to moderate power and burnup was considered excellent.
- Research Organization:
- Idaho National Laboratory (INL)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 968549
- Report Number(s):
- INL/JOU-09-15402
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 2 Vol. 393; ISSN 0022-3115; ISSN JNUMAM
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALLOYS
BURNUP
FABRICATION
FUEL PLATES
IRRADIATION
MEAT
METALLOGRAPHY
MICROSTRUCTURE
PERFORMANCE
Reduced Enrichment for Research and Test Reactors
SCANNING ELECTRON MICROSCOPY
TEST REACTORS
THICKNESS
irradiated U-7Mo/6061 Al alloy matrix dispersion f
low enriched uranium
microstructural development