Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries

dc.authoridcelik, yurdunaz/0000-0002-9211-8510
dc.authorwosidSarer, Basar/B-9445-2015
dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, Mehtap
dc.contributor.authorSarer, Basar
dc.contributor.authorCelik, Yurdunaz
dc.date.accessioned2024-08-04T20:35:36Z
dc.date.available2024-08-04T20:35:36Z
dc.date.issued2011
dc.departmentİnönü Üniversitesien_US
dc.description.abstractThe effects of evaluated nuclear data files on neutronics characteristics of a fusion-fission hybrid reactor have been analyzed; three-dimensional calculations have been made using the MCNP4C Monte Carlo Code for ENDF/B-VII T= 300K. JEFF-3.0 T= 300K, and CENDL-2 T= 300 K evaluated nuclear data files. The nuclear parameters of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, fissile fuel breeding and nuclear heating in a first wall, blanket and shield have been investigated for the mixture components of 90% Flibe (Li(2)BeF(4)) and 10% UF(4) for a blanket layer thickness of 50 cm. The contributions of each isotope of Flibe ((6)Li, (7)Li, (19)F, (9)Be) and UF(4) ((235)U, (238)U) to the integrated parameter values were calculated. The neutron wall load is assumed to be 10 MW/m(2). (C) 2011 Elsevier Ltd. All rights reserved.en_US
dc.identifier.doi10.1016/j.anucene.2011.08.007
dc.identifier.endpage2761en_US
dc.identifier.issn0306-4549
dc.identifier.issue12en_US
dc.identifier.scopus2-s2.0-80054892826en_US
dc.identifier.scopusqualityQ1en_US
dc.identifier.startpage2757en_US
dc.identifier.urihttps://doi.org/10.1016/j.anucene.2011.08.007
dc.identifier.urihttps://hdl.handle.net/11616/95469
dc.identifier.volume38en_US
dc.identifier.wosWOS:000297435300016en_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.subjectAPEXen_US
dc.subjectFusionen_US
dc.subjectFlibeen_US
dc.subjectNuclear heatingen_US
dc.subjectTritium breeding ratioen_US
dc.titleThree-dimensional neutronic calculations for a fusion breeder APEX reactor using some librariesen_US
dc.typeArticleen_US

Dosyalar