Monte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactor

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, Mehtap
dc.date.accessioned2024-08-04T20:41:20Z
dc.date.available2024-08-04T20:41:20Z
dc.date.issued2016
dc.departmentİnönü Üniversitesien_US
dc.description.abstractThis study analyzes the effects of certain heavy-metal-salt fluids on nuclear parameters in a fusion-fission hybrid reactor. Calculated parameters include the tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate, and fissile fuel breeding in the reactor's liquid first wall, blanket, and shield zones; gas production rates in the structural material of the reactor were calculated, as well. The fluid mixtures consisted of 93-85% Li20Sn50 + 5% SFG-PuO2 and 2-10% UO2, 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% NpO2, and 93-85% Li20Sn50 + 5% SFG-PuO2 and 2-10% UCO. The fluids were used in the liquid first wall, blanket, and shield zones of a fusion fission hybrid reactor system. A 3 cm wide beryllium (Be) zone was used for neutron multiplier between the liquid first wall and the blanket. The structural material used was 9Cr2WVTa ferritic steel, measuring 4 cm in width. Three-dimensional analyses were performed using the Monte Carlo code MCNPX-2.7.0 and the ENDF/B-VILO nuclear data library. (C) 2015 Elsevier Ltd. All rights reserved.en_US
dc.identifier.doi10.1016/j.pnucene.2015.10.017
dc.identifier.endpage109en_US
dc.identifier.issn0149-1970
dc.identifier.scopus2-s2.0-84948783978en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.startpage103en_US
dc.identifier.urihttps://doi.org/10.1016/j.pnucene.2015.10.017
dc.identifier.urihttps://hdl.handle.net/11616/97071
dc.identifier.volume86en_US
dc.identifier.wosWOS:000367111800012en_US
dc.identifier.wosqualityQ2en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherPergamon-Elsevier Science Ltden_US
dc.relation.ispartofProgress in Nuclear Energyen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectTBRen_US
dc.subjectMen_US
dc.subjectHeat deposition rateen_US
dc.subjectFissile fuel breedingen_US
dc.subjectRadiation damageen_US
dc.subjectMCNPX-2.7.0en_US
dc.titleMonte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactoren_US
dc.typeArticleen_US

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