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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Contact:
Mitchell Meyer
Advanced
Fuel Development
Argonne
National Laboratory - West
P.O.
Box 2528
Idaho Falls, ID 83403
Phone: 208 533 7461
Fax: 208 533 7863
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