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Meyer, M.K.; Clark, C.R.; Hayes, S.L.; Strain, R.V.; Hofman, G.L.; Snelgrove, J.L.; Park, J.M.; Kim, K.H.
Abstracts and papers of the 1999 International RERTR Meeting1999
Abstracts and papers of the 1999 International RERTR Meeting1999
AbstractAbstract
[en] 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 postirradiation 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. (author)
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Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States); 26 Megabytes; Oct 1999; [12 p.]; 22. international meeting on Reduced Enrichment for Research and Test Reactors (RERTR); Budapest (Hungary); 3-8 Oct 1999; Also available online: http://www.td.anl.gov/Programs/RERTR/web1999/Abstracts/Program.htm; 9 refs, 5 figs, 3 tabs
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