Argonne National Laboratory
RERTR
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

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

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

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ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department
9700 South Cass Ave., Argonne, IL 60439-4814
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Last modified on July 29, 2008 11:33 +0200