Burnup calculations using serpent code in accelerator driven thorium reactors

dc.contributor.authorKorkmaz, Mehmet Emin
dc.contributor.authorYi?it, Mustafa
dc.contributor.authorA?ar, Osman
dc.date.accessioned13.07.201910:50:10
dc.date.accessioned2019-07-29T19:28:06Z
dc.date.available13.07.201910:50:10
dc.date.available2019-07-29T19:28:06Z
dc.date.issued2013
dc.departmentFen-Edebiyat Fakültesi
dc.description.abstractIn this study, burnup calculations have been performed for a sodium cooled Accelerator Driven Thorium Reactor (ADTR) using the Serpent 1.1.16 Monte Carlo code. The ADTR has been designed for burning minor actinides, mixed Th-232 and mixed U-233 fuels. A solid Pb-Bi spallation target in the center of the core is used and sodium as coolant. The system is designed for a heating power of 2 000 MW and for an operation time of 600 days. For burnup calculations the Advanced Matrix Exponential Method CRAM (Chebyshev Rational Approximation Method) and different nuclear data libraries (ENDF7, JEF2.2, JEFF3.1.1) were used. The effective multiplication factor change from 0.93 to 0.97 for different nuclear data libraries during the reactor operation period.
dc.description.sponsorshipKaramanoglu Mehmetbey University Scientific Research Project [20-M-11]
dc.description.sponsorshipThis work was supported by Karamanoglu Mehmetbey University Scientific Research Project (20-M-11).
dc.identifier.doi10.3139/124.110358
dc.identifier.endpage197en_US
dc.identifier.issn0932-3902
dc.identifier.issue3en_US
dc.identifier.scopusqualityQ3
dc.identifier.startpage193en_US
dc.identifier.urihttps://doi.org/10.3139/124.110358
dc.identifier.urihttps://hdl.handle.net/20.500.12451/5987
dc.identifier.volume78en_US
dc.identifier.wosWOS:000323402800004
dc.identifier.wosqualityN/A
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherCarl Hanser Verlag
dc.relation.ispartofKERNTECHNIK
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.titleBurnup calculations using serpent code in accelerator driven thorium reactors
dc.typeArticle

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