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Vatulin, A.; Stetsky, Y.; Dobrikova, I.
ENS RRFM '99. Transactions. Oral presentations and posters1999
ENS RRFM '99. Transactions. Oral presentations and posters1999
AbstractAbstract
[en] The estimation of neutron-physical, heat and hydraulic parameters of the IR-8 research reactor with low enriched uranium (LEU) fuel was performed. Two fuel assembly (FA) designs were reviewed: IRT-4M with the tubular type fuel elements and IRT-MR with the rod type fuel elements. UO2-Al dispersion 19.75% enrichment fuel is used in both cases. The results of the calculations were compared with main parameters of the reactor, using the current IRT-3M FA with 90% high enriched uranium (HEU) fuel. The results of these comparisons showed that during the LEU conversion of the reactor the cycle length, excess reactivity and peak power of the IRT-MR type FA are higher than for the IRT-3M type FA and IRT-4M type FA. (author)
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European Nuclear Society, Berne (Switzerland); Belgian Nuclear Society (Belgium); International Atomic Energy Agency, Vienna (Austria); 217 p; 1999; p. 50-54; 3. International Topical Meeting on Research Reactor Fuel Management (RRFM '99); Bruges (Belgium); 28-30 Mar 1999; Country of input: International Atomic Energy Agency (IAEA); 11 refs, 7 figs, 4 tabs
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Report
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Conference
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ACTINIDE COMPOUNDS, ACTINIDES, CHALCOGENIDES, ELEMENTS, ENRICHED URANIUM, FUEL ELEMENTS, FUEL RODS, ISOTOPE ENRICHED MATERIALS, MATERIALS, METALS, OXIDES, OXYGEN COMPOUNDS, PHYSICS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, URANIUM, URANIUM COMPOUNDS, URANIUM OXIDES
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