Abstracts and Available Papers Presented at the
2002 International RERTR Meeting

PROGRESS IN IRRADIATION PERFORMANCE OF EXPERIMENTAL URANIUM–MOLYBDENUM DISPERSION FUEL

Gerard L. Hofman and Mitchell K. Meyer*

Argonne National Laboratory
9700 South Cass Avenue, Argonne, IL 60439 USA

*Argonne National Laboratory-West
P.O. Box 2528, Idaho Falls, ID 83403-2528 USA

ABSTRACT

High-density dispersion fuel experiment, RERTR-4, was removed from the Advanced Test Reactor (ATR) after reaching a peak U-235 burnup of ~80% and is presently undergoing postirradiation examination at the ANL alpha-gamma hot cells.  This test consists of 32 mini fuel plates of which 27 were fabricated with nominally 6 and 8 g cm^-3 atomized and machined uranium alloy powders containing 7 wt% and 10 wt% molybdenum.  In addition, two miniplates containing solid U-10 wt% Mo foils and three containing 6 g cm^-3 U₃Si₂ are part of the test. The results of the postirradiation examination and analysis of RERTR-4 in conjunction with data from previous tests performed to lower burnup will be presented.

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