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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