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.