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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Contact:
Dr.
Gerard Hofman
Senior Metallurgist
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439 USA
Phone: (630) 252-6683
Fax: (630) 252-5161
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