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

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Abstracts and Available Papers Presented at the
2000 International RERTR Meeting


M.K. Meyer, G.L. Hofman*, R.V. Strain*, C.R. Clark, and J.R. Stuart
Argonne National Laboratory
P.O. Box 2528, Idaho Falls ID 83403
*1700 S. Cass Avenue, Argonne, IL 60439, USA


The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix U-Mo alloy dispersion fuels under high-temperature, high-fission-rate conditions. Initial postirradiation examination of RERTR-3 fuel specimens has concentrated on binary U-Mo atomized fuels. The rate of matrix aluminum depletion was found to be higher than predictions based on low temperature irradiation data. Wavelength Dispersive X-ray Spectroscopy (WDS) indicates that aluminum is present in the interior of the fuel particles. WDS data is supported by a mass and volume balance calculation performed on the basis of image analysis results. The depletion of matrix aluminum seems to have no detrimental effects on fuel performance under the conditions tested to date.

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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