The neutronic calculations for some fluids, libraries and structural materials in a hybrid reactor system

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:41:21Z
dc.date.available2024-08-04T20:41:21Z
dc.date.issued2015
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn the present investigation, a hybrid reactor system was designed by using 100% Flibe, 90% Flibe-10% ThF4, 90 % Flibe-10% UF4 fluids, ENDF/B-VII, JEFF-3.1, JENDL-4.0, ROSFOND, BROND-2.2, CENDL-3.1 evaluated nuclear data libraries and Ferritic Steel, 9Cr2WVTa, V4Cr4Ti, SiC structural materials. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion-fission hybrid reactor system. The nuclear parameters of a fusion-fission hybrid reactor such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate were computed in liquid first wall, blanket and shield zones. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code.en_US
dc.description.sponsorshipInonu University Research fund [2011/44]en_US
dc.description.sponsorshipThis work was supported by Inonu University Research fund with the project number 2011/44.en_US
dc.identifier.doi10.3139/124.110530
dc.identifier.endpage453en_US
dc.identifier.issn0932-3902
dc.identifier.issue5en_US
dc.identifier.scopus2-s2.0-84949505323en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.startpage449en_US
dc.identifier.urihttps://doi.org/10.3139/124.110530
dc.identifier.urihttps://hdl.handle.net/11616/97081
dc.identifier.volume80en_US
dc.identifier.wosWOS:000364540000005en_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.subject1st Wallen_US
dc.subjectFusionen_US
dc.subjectDesignen_US
dc.titleThe neutronic calculations for some fluids, libraries and structural materials in a hybrid reactor systemen_US
dc.typeArticleen_US

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