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Lajoie, M.A.; Marleau, G.; Martin, N.; H'ebert, A.
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
AbstractAbstract
[en] The analysis of VHTR fuel tends to be difficult, when using deterministic methods currently employed in lattice codes, notably because of limitations on geometry representation, and the stochastic positioning of spherical elements. The method proposed here and implemented in the lattice code DRAGON is to generate the positions of multi-layered spheres using random sequential addition, and to analyze the resulting geometry using a full three-dimensional spherical collision probability method. The preliminary validation runs are consistent with results obtained using the Monte-Carlo method. Comparisons have also been made with two double-heterogeneity models already available in DRAGON. (authors)
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2010; 12 p; American Nuclear Society - ANS; La Grange Park, Illinois (United States); PHYSOR 2010: Advances in Reactor physics to Power the Nuclear Renaissance; Pittsburgh, PA (United States); 9-14 May 2010; ISBN 978-0-89448-079-9;
; Country of input: France; 13 refs.

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Book
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Conference
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CALCULATION METHODS, CONFIGURATION, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EVALUATION, EXPERIMENTAL REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, MATERIALS, MATHEMATICAL SOLUTIONS, MATHEMATICS, NUMERICAL SOLUTION, POWER REACTORS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, TESTING, THERMAL REACTORS
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