Please use this identifier to cite or link to this item: http://hdl.handle.net/11452/21030
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dc.contributor.authorYapıcı, Hüseyin-
dc.contributor.authorÇürüttü, İlyas-
dc.contributor.authorÖzceyhan, Veysel-
dc.date.accessioned2021-07-05T06:08:19Z-
dc.date.available2021-07-05T06:08:19Z-
dc.date.issued1999-
dc.identifier.citationYapıcı, H. vd. (1999). "Potential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRs". Annals of Nuclear Energy, 26(9), 821-832.en_US
dc.identifier.issn0306-4549-
dc.identifier.urihttps://doi.org/10.1016/S0306-4549(98)00093-0-
dc.identifier.urihttps://www.sciencedirect.com/science/article/pii/S0306454998000930-
dc.identifier.urihttp://hdl.handle.net/11452/21030-
dc.description.abstractIn this study, neutronic performances of the (D,T) driven hybrid blankets, fuelled with UC2 and UF4, are investigated under first wall load of 5 MW/m(2). The fissile fuel zone is considered to be cooled with three coolants: gas (He or CO2), flibe (Li2BeF4), and natural lithium. The behaviour of the UC2 and UF4 fuels are observed during 48 months for discrete time intervals of Delta t = 15 days and by a plant factor of 75%. At the end of the operation time, calculations have shown that Cumulative Fissile Fuel Enrichment (CFFE) values varied between 5 and 8.5% depending on the fuel and coolant type. The best enrichment performance is obtained in UF4 fuelled blanket with flibe coolant, followed by gas and natural lithium coolant. CFFE reaches maximum value (8.51%) in UF4 fuelled blanket (in row #1) and flibe coolant mode after 48 months. The lowest CFFE value (4.71%) is in UC2 fuelled blanket (in row #8) and natural lithium coolant at the end of the operation period. This enrichment would be sufficient for LWR reactor. At the beginning of the operation, tritium breeding ratio (TBR) values were 1.090, 1.3301 and 1.2489 in UC2 fuelled blanket and 1.0772, 1.2433 and 1.1533 in UF4 fuelled blanket for flibe, natural lithium and gas coolant, respectively. At the end of the operation, TBR reach 1.1820, 1.3983 and 1.3138 in UC2 fuelled blanket and 1.2041,1.3266 and 1.2407 in UF4 fuelled blanket for flibe, natural lithium and gas coolant, respectively. Nuclear quality of the plutonium increases linearly during the operation period. The isotopic percentage of Pu-240 is higher than 5% in UF4 and UC2 fuel with flibe coolant, so that the plutonium component in these modes can never reach a nuclear weapon grade quality during the operation period. This is very important factor for safeguarding. The isotopic percentage of Pu-240 is lower than 5% in UC2 fuel with gas and natural lithium coolant. In these modes, operation period must be increased to safeguarding.en_US
dc.language.isoenen_US
dc.publisherPergamon-Elsevier Scienceen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectNuclear science & technologyen_US
dc.subjectRejuvenationen_US
dc.subjectCandu spent fuelen_US
dc.subjectBlanketsen_US
dc.titlePotential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRsen_US
dc.typeArticleen_US
dc.identifier.wos000078470200005tr_TR
dc.identifier.scopus2-s2.0-0033149883tr_TR
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergitr_TR
dc.contributor.departmentUludağ Üniversitesi/Mühendislik-Mimarlık Fakültesi.tr_TR
dc.identifier.startpage821tr_TR
dc.identifier.endpage832tr_TR
dc.identifier.volume26tr_TR
dc.identifier.issue9tr_TR
dc.relation.journalAnnals of Nuclear Energyen_US
dc.contributor.buuauthorKırbıyık, Mehmet-
dc.relation.collaborationYurt içitr_TR
dc.subject.wosNuclear science & technologyen_US
dc.indexed.wosSCIEen_US
dc.indexed.scopusScopusen_US
dc.wos.quartileQ3en_US
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