Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:40:12Z
dc.date.available2024-08-04T20:40:12Z
dc.date.issued2015
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, salt-heavy metal mixtures consisting of 93-85% Li20Sn80+5% SFG-PuO2 and 2-10% UO2, 93-85% Li20Sn80+5% SFG-PuO2 and 2-10% NpO2, and 93-85% Li20Sn80+5% SFG-PuO2 and 2-10% UCO were used as fluids. The fluids were used in the liquid first wall, blanket, and shield zones of a fusion-fission hybrid reactor system. A beryllium (Be) zone with a width of 3 cm was used for neutron multiplicity between the liquid first wall and the blanket. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. The contributions of each isotope in the fluids to the nuclear parameters, such as tritium breeding ratio (TBR), energy multiplication factor (M), and heat deposition rate, of the fusion-fission hybrid reactor were calculated in the liquid first wall, blanket, and shield zones. Three-dimensional analyses were performed using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.en_US
dc.identifier.doi10.3139/124.110479
dc.identifier.endpage52en_US
dc.identifier.issn0932-3902
dc.identifier.issue1en_US
dc.identifier.scopus2-s2.0-84928951740en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.startpage45en_US
dc.identifier.urihttps://doi.org/10.3139/124.110479
dc.identifier.urihttps://hdl.handle.net/11616/96773
dc.identifier.volume80en_US
dc.identifier.wosWOS:000351750800006en_US
dc.identifier.wosqualityQ4en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherCarl Hanser Verlagen_US
dc.relation.ispartofKerntechniken_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectApex Reactoren_US
dc.subjectRadiation-Damageen_US
dc.subjectStructural Materialen_US
dc.subjectSelf-Sufficiencyen_US
dc.subjectFusionen_US
dc.subjectWallen_US
dc.titleNeutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo methoden_US
dc.typeArticleen_US

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