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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
1997 International RERTR Meeting

Design and Fabrication of High Density
Uranium Dispersion Fuels

L. T. C. Wiencek#, M. K. Meyer, D. J. McGann# and C. R. Clark

Engineering Division
Argonne National Laboratory
Idaho Falls, ID

#Energy Technology Division
Argonne National Laboratory
Chicago, IL

Abstract

Twelve different uranium alloys and compounds with uranium densities greater than 13.8 g/cc were fabricated into fuel plates. Sixty-four experimental fuel plates, referred to as microplates, with overall dimensions of 76.2 mm x 22.2 mm x 1.3 mm and elliptical fuel zone of nominal dimensions of 51 mm x 9.5 mm, began irradiation in the Advanced Test Reactor on August 23, 1997. The fuel test matrix consists of machined or comminuted (compositions are in weight %) U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-lPt, U-6Mo-0.6Ru, U-10Mo-0.05Sn, U2Mo and U3Si2 (as a control). The low enriched (235U<20%) fuel materials were cast, powdered, mixed with aluminum dispersant at a volume ratio of 1:3, compacted and hot rolled to form the microplates. Spherical atomized powders of two fuels, U-l0Mo and U3Si2, were utilized to make microplates and included in the irradiation test as well. The experimental design and fabrication steps employed in the selection and production of the fueled microplates is discussed.


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Energy Technology Division
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Last modified on July 29, 2008 11:34 +0200