The effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport code

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.authorwosidSarer, Basar/B-9445-2015
dc.contributor.authorGunay, Mehtap
dc.contributor.authorSarer, Basar
dc.contributor.authorKasap, Hizir
dc.date.accessioned2024-08-04T20:37:47Z
dc.date.available2024-08-04T20:37:47Z
dc.date.issued2014
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, 99-95% Li20Sn80-1-5% SFG-PuO2 were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. The parameters of radiation damage are proton, deuterium, tritium, He-3 and He-4 gas production rates. In this study, the effects of the selected fluid on the radiation damage, in terms of individual as well as total isotopes in the structural material, were investigated for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent version of the MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library. Published by Elsevier Ltd.en_US
dc.identifier.doi10.1016/j.anucene.2013.07.038
dc.identifier.endpage161en_US
dc.identifier.issn0306-4549
dc.identifier.scopus2-s2.0-84883122566en_US
dc.identifier.scopusqualityQ1en_US
dc.identifier.startpage157en_US
dc.identifier.urihttps://doi.org/10.1016/j.anucene.2013.07.038
dc.identifier.urihttps://hdl.handle.net/11616/96184
dc.identifier.volume63en_US
dc.identifier.wosWOS:000327829400017en_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.subjectHybrid reactoren_US
dc.subjectRadiation damageen_US
dc.subjectStructural materialen_US
dc.subjectMCNPX-2.7.0en_US
dc.titleThe effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport codeen_US
dc.typeArticleen_US

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