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Rabiti, C.; Palmiotti, G.; Assawaroongruengchot, M.; Adams, B.M.
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] This paper describes a comparative study of two Uncertainty Quantification (UQ) techniques for reactor neutronics analysis. Adjoint- and sampling-based uncertainty quantification approaches are applied to a simplified model of a sodium-cooled fast reactor to evaluate uncertainty in four integral parameters (void reactivity, Doppler reactivity, Keff, and control rod reactivity). Results obtained with the two UQ methodologies are compared and discussed. This preliminary work, performed in a well-studied field like neutronics, will inform sensitivity and uncertainty method selection for future calculations in other disciplines like coupled neutronics/thermo-hydraulics. (authors)
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2010; 12 p; American Nuclear Society - ANS; La Grange Park, Illinois (United States); PHYSOR 2010: International Conference on 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; 10 refs.
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