Abstracts and Available Papers Presented at the 2005 International RERTR Meeting
PROGRESS OF
THE KOMO-3 IRRADIATION TEST FOR VARIOUS U-MO DISPERSION
AND MONOLITHIC FUELS TO OVERCOME THE INTERACTION PROBLEM
IN U-MO/AL DISPERSION FUEL
Korea Atomic Energy
Research Institute
150 Dukjin-dong, Yuseong-gu, Daejeon 305-353, Korea
ABSTRACT
The next irradiation test (KOMO-3) has been planned
from the aspect of overcoming the problems which were
revealed in the latest irradiation tests (KOMO-2). The
main reason for the problems was found to be an
interaction between the U-Mo particles and the Al
matrix. The interaction problem could be solved by a
smaller interface area such as a monolithic fuel and a
reaction retardation by a third element addition into
the Al matrix or U-Mo fuel particles. In the KOMO-3
test, multi-core fuel meat and larger U-Mo particles are
applied for smaller interface area. In addition, U-7Mo-X
(X=0.2Si and 1.0 Zr) fuel particles and Al-X alloys
(X=0.5%Si and 2.0%Si) are chosen for an interaction
retardation. Multi-core fuel meat consists of 4 U-Mo
rods of 2.0 mm in diameter in aluminum matrix. The
equivalent U density corresponds to 6.0 g-U/cc and the
highest temperature in the irradiation was estimated to
be about 322 °C. Three kinds of larger U-Mo particles,
which are 100-212 μm, 212-300 μm, and 300-425 μm, were
prepared by atomization methods. The U densities of the
larger U-Mo particle dispersion fuel meats were selected
as 4.5 g-U/cc from the safety aspect.
Contact: Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161
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