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dc.contributor.authorGiudicelli, Guillaume Louis
dc.contributor.authorSmith, Kord
dc.contributor.authorForget, Benoit
dc.date.accessioned2020-05-05T15:00:32Z
dc.date.available2020-05-05T15:00:32Z
dc.date.issued2017-09
dc.date.submitted2017-09
dc.identifier.issn0306-4549
dc.identifier.urihttps://hdl.handle.net/1721.1/125011
dc.description.abstractThe process of generating multi-group cross section data to be used in full core 3D transport models requires not only accurate resonance self-shielding methods, but also some form of equivalence method in order to precisely preserve reaction rates of spectral geometry calculations. This paper presents extensions of the traditional concepts of local reaction rate preservation (common in discontinuity factor, SPH, and BBH methods), to derive a new state-of-the-art transport equivalence method that incorporates angular flux jump conditions that provide polar angle neutron current preservation. This method is tested on numerous fixed-source pin-cell problems by condensing fine energy resonance fluxes and cross sections. The method is demonstrated to precisely preserve all spectral geometry multi-group reaction rates as well as polar angle neutron currents for a wide range of cross section resonance heights, fuel pin diameters, coolant densities, and group energy widths. Keywords: Neutron transport; Self-shielding; Equivalence; Condensation; Discontinuity factors; Jump conditionsen_US
dc.description.sponsorshipUnited States. Department of Energy. Nuclear Energy University Program (Grant DE-NE0008578)en_US
dc.language.isoen
dc.publisherElsevier BVen_US
dc.relation.isversionofhttp://dx.doi.org/10.1016/j.anucene.2017.09.024en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceProf. Forget via Chris Sherratten_US
dc.titleGeneralized equivalence methods for 3D multi-group neutron transporten_US
dc.typeArticleen_US
dc.identifier.citationGiudicelli, Guillaume Louis, Smith, Kord, and Forget, Benoit. "Generalized equivalence methods for 3D multi-group neutron transport." Annals of Nuclear Energy 112 (February 2018): 9-16 © 2017 Elsevier Ltden_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.relation.journalAnnals of Nuclear Energyen_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dc.date.updated2019-09-26T13:50:11Z
dspace.date.submission2019-09-26T13:50:13Z
mit.journal.volume112en_US


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