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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Contact:
Mr.
Thomas Wiencek
Engineering Specialist
Energy Technology
Division
Argonne National
Laboratory
9700 South Cass Avenue
Argonne, IL 60439 USA
Phone: (630)
252-5020
Fax:
(630) 252-9232