Abstracts and Available Papers Presented at the
2000 International RERTR Meeting
METALLOGRAPHIC ANALYSIS OF IRRADIATED
RERTR-3 FUEL TEST SPECIMENS
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
and
*1700 S. Cass Avenue, Argonne, IL 60439, USA
ABSTRACT
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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Contact:
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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