Implementation of multi-group cross-section methodology in BGCore MC-depletion code

Emil Fridman, Eugene Shwageraus, Alex Galperin

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

35 Scopus citations

Abstract

BGCore is a software package for comprehensive computer simulation of nuclear reactor systems and their fuel cycles. The BGCore interfaces Monte Carlo particles transport code MCNP4C with a SARAF module - an independently developed code for calculating in-core fuel composition and spent fuel emissions following discharge. In BGCore system, depletion coupling methodology is based on the multi-group approach that significantly reduces computation time and allows tracking of large number of nuclides during calculations. In this study, burnup calculation capabilities of BGCore system were validated against well established and verified, computer codes for thermal and fast spectrum lattices. Very good agreement in k eigenvalue and nuclide densities prediction was observed for all cases under consideration. In addition, decay heat prediction capabilities of the BGCore system were benchmarked against the most recent edition of ANS Standard methodology for UO2 fuel decay power prediction in LWRs. It was found that the difference between ANS standard data and that predicted by the BGCore does not exceed 5%.

Original languageEnglish
Title of host publicationInternational Conference on the Physics of Reactors 2008, PHYSOR 08
PublisherPaul Scherrer Institut
Pages814-821
Number of pages8
ISBN (Print)9781617821219
StatePublished - 1 Jan 2008
EventInternational Conference on the Physics of Reactors 2008, PHYSOR 08 - Interlaken, Switzerland
Duration: 14 Sep 200819 Sep 2008

Publication series

NameInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Volume1

Conference

ConferenceInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Country/TerritorySwitzerland
CityInterlaken
Period14/09/0819/09/08

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