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
2003 International RERTR Meeting


C.R. Clark, G.C. Knighton, M.K. Meyer, G.L. Hofman*

Argonne National Laboratory
P.O. Box 2528
Idaho Falls, Idaho 83403-2528

*9700 Cass Avenue
Argonne, Illinois 60439


Initial fabrication results of U-Mo dispersion fuel have shown a practical uranium loading limit below that required to successfully convert some of the targeted research reactors to low-enriched uranium.  In addition, irradiation tests have shown that U-Mo dispersion fuel suffers from interaction between the fuel and the aluminum matrix at higher temperatures. A potential solution to mitigate these phenomena is to use a fuel alloy foil in place of the fuel-aluminum dispersion. This monolithic fuel provides a lower fuel-matrix interfacial surface area and a much higher uranium density than dispersion type fuel. Lacking the compliant matrix of dispersion fuel types, monolithic fuel production requires the development of new fabrication methods. Research efforts at Argonne National Laboratory have resulted in the demonstration of a viable monolithic fuel plate production method, which is described in this paper.

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Mr. Curtis R. Clark
Materials Engineer, Fuel Development
Argonne National Laboratory
Nuclear Technology Division
P.O. Box 2528
Idaho Falls, ID 83403-2528 USA
Phone:  +1 (208) 533-7701
Fax:      +1 (208) 533-7340
E-mail:  [email protected]

2016 RERTR Meeting

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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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9700 South Cass Ave., Argonne, IL 60439-4814
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Last modified on July 29, 2008 11:33 +0200