Estimation of neutronic performance in a hybrid reactor with regression analysis

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dc.contributor.authorAcır, Adem
dc.contributor.authorAlakoç, Nilüfer Pekin
dc.contributor.authorYıldız, Kadir
dc.date.accessioned13.07.201910:50:10
dc.date.accessioned2019-07-16T09:16:05Z
dc.date.available13.07.201910:50:10
dc.date.available2019-07-16T09:16:05Z
dc.date.issued2009
dc.departmentMühendislik Fakültesi
dc.description.abstractThis study presents regression analysis method used for prediction and investigation of neutronic performance in a hybrid reactor using UO(2) fuel and Flibe (Li(2)BeF(4)) coolant. The (235)U fraction is increased gradually from 0 to 4% stepped by 1% and the (6)Li fraction within the Flibe coolant is enriched gradually to 30, 60 and 90% from 7.5%. Relations between (235)U fuel fraction and lithium ((6)Li) enrichment are investigated for the estimation of neutronic performance as the tritium breeding ratio (TBR), energy multiplication factor (M), total fission rate (I (f)) pound, (238)U (n,gamma) reaction and fissile fuel breeding (FFB) in the hybrid reactor. Regression analysis by results obtained by using the code (XSDRNPM/SCALE5) for TBR, M, I (f) pound, (238)U (n,gamma) and FFB are performed. The results of the regression analysis and the values obtained by using the code (XSDRNPM/SCALE5) are compared with respect to the TBR, M, I (f) pound, (238)U (n,gamma) and FFB of the reactor. The values calculated from the obtained formulations with regression analysis are found to be in good agreement with results obtained by using the code (XSDRNPM/SCALE5). It is observed that the derived equations from regression analysis could provide an accurate computation of the neutronic performances so that these equations could use for the prediction of TBR, M, I (f) pound, (238)U (n,gamma) and FFB. In addition, correlation matrix is calculated to determine the degree of relationship between variables as TBR, M, I (f) pound, (238)U (n,gamma) and FFB.
dc.identifier.doi10.1007/s10894-009-9217-y
dc.identifier.endpage433en_US
dc.identifier.issn0164-0313
dc.identifier.issue4en_US
dc.identifier.scopusqualityQ2
dc.identifier.startpage427en_US
dc.identifier.urihttps://doi.org/10.1007/s10894-009-9217-y
dc.identifier.urihttps://hdl.handle.net/20.500.12451/4528
dc.identifier.volume28en_US
dc.identifier.wosWOS:000271201700018
dc.identifier.wosqualityN/A
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherSpringer
dc.relation.ispartofJournal of Fusion Energy
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/openAccess
dc.subjectRegression Analysis
dc.subjectHybrid Reactor
dc.subjectCorrelation
dc.subjectTritium Breeding Ratio
dc.subjectFissile Fuel Breeding
dc.subjectNeutronic Performance
dc.titleEstimation of neutronic performance in a hybrid reactor with regression analysis
dc.typeArticle

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