Abstracts and Available Papers Presented at the
2003 International RERTR Meeting
Modeling RERTR Experimental Fuel Plates using the PLATE Code
S. L. Hayes and M. K. Meyer
Nuclear Technology
Division
Argonne National
Laboratory, Idaho Falls, ID 83403-2528 – USA
G. L. Hofman and J. L. Snelgrove
Nuclear Engineering
Division
Argonne National
Laboratory, 9700 S. Cass Ave., Argonne, IL 60439-4815 – USA
R. A. Brazener
Department of Nuclear
Engineering
Penn State
University, University Park, PA 16804 – USA
ABSTRACT
Modeling results using the PLATE dispersion fuel performance code are presented for the U-Mo/Al experimental fuel plates from the RERTR-1, ‑2, -3 and -5 irradiation tests. Agreement of the calculations with experimental data obtained in postirradiation examinations of these fuels, where available, is shown to be good. Use of the code to perform a series of parametric evaluations highlights the sensitivity of U-Mo dispersion fuel performance to fabrication variables, especially fuel particle shape and size distributions.
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Contact:
Mr.
Steven L. Hayes
Manager,
Fuels Testing & Analysis
Argonne
National Laboratory, West
P.O.
Box 2528
Idaho
Falls, ID 83403-2528 USA
Phone: (208) 533-7255
Fax: (208) 533-7863
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