Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
1997 International RERTR Meeting

Selection and Microstructures of High Density
Uranium Alloys

M.K. Meyer, C. L. Trybus, G. L. Hofman, S. M. Frank, and T.C. Wiencek

Argonne National Laboratory
Idaho Falls, ID
Argonne, IL

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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Mitchell Meyer
Advanced Fuel Development
Argonne National Laboratory - West
P.O. Box 2528
Idaho Falls, ID 83403

Phone:  208 533 7461
Fax:      208 533 7863

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Last modified on July 29, 2008 11:33 +0200