Potential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRs

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dc.contributor.authorYapici, H
dc.contributor.authorÇürüttü, I
dc.contributor.authorÖzceyhan, V
dc.contributor.authorKirbiyik, M
dc.date.accessioned2024-09-18T21:03:13Z
dc.date.available2024-09-18T21:03:13Z
dc.date.issued1999
dc.departmentHatay Mustafa Kemal Üniversitesien_US
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. (C) 1999 Elsevier Science Ltd. All rights reserved.en_US
dc.identifier.doi10.1016/S0306-4549(98)00093-0
dc.identifier.endpage832en_US
dc.identifier.issn0306-4549
dc.identifier.issue9en_US
dc.identifier.scopus2-s2.0-0033149883en_US
dc.identifier.scopusqualityQ1en_US
dc.identifier.startpage821en_US
dc.identifier.urihttps://doi.org/10.1016/S0306-4549(98)00093-0
dc.identifier.urihttps://hdl.handle.net/20.500.12483/13313
dc.identifier.volume26en_US
dc.identifier.wosWOS:000078470200005en_US
dc.identifier.wosqualityQ3en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherPergamon-Elsevier Science Ltden_US
dc.relation.ispartofAnnals of Nuclear Energyen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectCandu Spent Fuelen_US
dc.subjectRejuvenationen_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

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