Abstracts and Available Papers Presented at the
2004 International RERTR Meeting
PIE OF THE 2ND IRRADIATION TEST (KOMO-2) FOR THE ATOMIZED U-MO DISPERSION ROD FUELS AT KAERI
C.K. Kim, H.J. Ryu, D.B. Lee, S.J Oh, K.H Kim, J.M
Park, Y.S. Choo, D.G. Park, H.T. Chae, C.S. Lee, D.S
Sohn
KAERI 150 Duckjin-dong, Yuseong-ku, Daejeon city,
Korea
ABSTRACT
Two U-7wt.%Mo dispersion fuel rods with different fuel particle sizes, two U-7wt.%Mo dispersion fuel rods surface-treated with pre-oxidation and Ni coating, one U-7wt.%Mo dispersion fuel rod with a poison material of Er2O3, a U-9wt.%Mo dispersion fuel rod, and a U3Si dispersion fuel rod were loaded in the KOMO-test (the 2nd irradiation test of U-Mo fuels in HANARO by KAERI). In addition, the monolithic U-Mo ring fuel was loaded to develop higher U-density fuel. The fuel assembly with the above 10 fuel rods was irradiated in HAHARO successfully from January 9, 2003 to January 27, 2004. After cooling them for about 3 months, the PIE has been performed. Most of the fuel particles were interacted with the Al matrix in the central area of the rod-type U-Mo dispersion fuels with a high linear power and a higher burnup than 60 at.%. Some large pores were observed between the particles in the central area of the fuel rods. However the swellings of the fuel meats are not large, at less than 17 %. The fuel of a larger particle-size distribution showed a better stability than the fuel of a smaller particle-size distribution. Any surface treatments were observed to have no improvement on the oxidation layer formation of the cladding surface. U3Si dispersion fuel used as a reference showed a much lesser interaction with the matrix Al when compared with the U-Mo dispersion fuel. In an examination for the tubular monolithic U-Mo fuel abnormal phenomena such as many bubbles and a large swelling happened due to an unexpected contamination of the silicon from the quartz tube used for a mold during melting & casting process.
PDF version available
The full paper
is available in Adobe Systems Inc.'s Portable Document
Format (PDF) and can be read and downloaded using
Adobe's Acrobat Reader software. This software needs to
be installed on your computer either as a separate
program or as part of an Internet browser in order to
read this paper. Adobe Acrobat Reader can be downloaded
free of charge from Adobe's site on the World Wide
Web.
If Adobe's Acrobat Reader is installed on
your computer, click here
to access the full paper in PDF format.
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
![]()


