Contributions of each isotope in some fluids on neutronic performance in a fusion-fission hybrid reactor: a Monte Carlo method

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dc.authorwosidSarer, Basar/B-9445-2015
dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.contributor.authorSarer, B.
dc.contributor.authorKasap, H.
dc.date.accessioned2024-08-04T20:39:45Z
dc.date.available2024-08-04T20:39:45Z
dc.date.issued2014
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn the present investigation, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa ferritic steel structural material and 99-95 % Li20Sn80-1-5 % SFG-Pu, 99-95 % Li20Sn80-1-5 % SFG-PuF4, 99-95 % Li20Sn80-1-5 % SFG-PuO2 the molten salt-heavy metal mixtures, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium zone with the width of 3 cm was used for the neutron multiplicity between liquid first wall and blanket. The contributions of each isotope in fluids on the nuclear parameters of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, heat deposition rate were computed in liquid first wall, blanket and shield zones. Three-dimensional analyses were performed by using Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.en_US
dc.identifier.doi10.1007/s12648-014-0496-4
dc.identifier.endpage866en_US
dc.identifier.issn0973-1458
dc.identifier.issn0974-9845
dc.identifier.issue8en_US
dc.identifier.scopus2-s2.0-84903625193en_US
dc.identifier.scopusqualityQ3en_US
dc.identifier.startpage861en_US
dc.identifier.urihttps://doi.org/10.1007/s12648-014-0496-4
dc.identifier.urihttps://hdl.handle.net/11616/96489
dc.identifier.volume88en_US
dc.identifier.wosWOS:000344777800012en_US
dc.identifier.wosqualityQ2en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherIndian Assoc Cultivation Scienceen_US
dc.relation.ispartofIndian Journal of Physicsen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectHybrid reactoren_US
dc.subjectTritium breeding ratioen_US
dc.subjectHeat deposition rateen_US
dc.subjectMCNPX-2.7.0en_US
dc.titleContributions of each isotope in some fluids on neutronic performance in a fusion-fission hybrid reactor: a Monte Carlo methoden_US
dc.typeArticleen_US

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