Abstracts and Available Papers Presented at the
1999 International RERTR Meeting

Irradiation Behavior of Uranium-Molybdenum Dispersion Fuel:
 Fuel Performance Data from RERTR-1 and RERTR–2

M.K. Meyer, G.L. Hofman*, J.L. Snelgrove*, C.R. Clark, S.L. Hayes, and R.V. Strain*
Argonne National Laboratory
P.O. Box 2528, Idaho Falls ID 83403 and
*1700 S. Cass Avenue, Argonne, IL 60439, USA

J.M. Park, K.H. Kim
Korea Atomic Energy Research Institute
150, Dukjin-Dong, Yusong-Ku, Taejon, 305-353, Korea

ABSTRACT

This paper presents quantitative data on the irradiation behavior of uranium-molybdenum fuels from the low temperature RERTR-1 and -2 experiments.   Fuel swelling measurements of U-Mo fuels at ~40% and ~70% burnup are presented.  The rate of fuel-matrix interaction layer growth is estimated. Microstructures of fuel in the pre- and post-irradiation condition were compared.  Based on these data, a qualitative picture of the evolution of the U-Mo fuel microstructure during irradiation has been developed.   Estimates of uranium-molybdenum fuel swelling and fuel-matrix interaction under high-power research reactor operating conditions are presented.

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