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Hofman, G.L.; Meyer, M.K.; Snelgrove, J.L.; Dietz, M.L.; Strain, R.V.; Kim, K-H.
Abstracts and papers of the 1999 International RERTR Meeting1999
Abstracts and papers of the 1999 International RERTR Meeting1999
AbstractAbstract
[en] Results from the postirradiation examinations of microplates irradiated in the RERTR-1 and -2 experiments in the ATR have shown several binary and ternary U-Mo alloys to be promising candidates for use in aluminum-based dispersion fuels with uranium densities up to 8 to 9 g/cm3. Ternary alloys of uranium, niobium, and zirconium performed poorly, however, both in terms of fuel/matrix reaction and fission-gas-bubble behavior, and have been dropped from further study. Since irradiation temperatures achieved in the present experiments (approximately 70 deg. C) are considerably lower than might be experienced in a high-performance reactor, a new experiment is being planned with beginning-of-cycle temperatures greater than 200 deg. C in 8-g U/cm3 fuel. (author)
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Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States); 26 Megabytes; Oct 1999; [15 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; 3 refs, 13 figs, 2 tabs
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ALLOY NUCLEAR FUELS, ALLOY SYSTEMS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, IRRADIATION REACTORS, MATERIALS, MATERIALS TESTING REACTORS, NUCLEAR FUELS, PHYSICAL PROPERTIES, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID FUELS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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