Abstracts and Available Papers Presented at the
1997 International RERTR Meeting
Selection and Microstructures of
M.K. Meyer, C. L. Trybus, G. L. Hofman, S. M. Frank, and T.C. Wiencek
Argonne National Laboratory
Idaho Falls, ID
Twelve uranium alloys have been selected for incorporation into very high density aluminum dispersion fuel plates for irradiation testing. These alloys are (nominally) U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-2Mo-lNb-lZr, U-6Mo-lPt, U-6Mo-0.6Ru, U-6Mo-0.6Si, and U-10Mo-O.OSSn. The rationale for selection of these fuels based on gamma phase stability, reports of good irradiation performance, and high uranium density will be discussed. The microstructures of these fuels were examined by SEM/EDS and XRD at three stages during the powder fabrication process. Microstructures of selected alloys are discussed.
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Advanced Fuel Development
Argonne National Laboratory - West
P.O. Box 2528
Idaho Falls, ID 83403
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