Contribution of each isotope in structral material on radiation damage in a hybrid reactor

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, Mehtap
dc.date.accessioned2024-08-04T20:43:03Z
dc.date.available2024-08-04T20:43:03Z
dc.date.issued2016
dc.departmentİnönü Üniversitesien_US
dc.descriptionInternational Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT) -- APR 28-30, 2016 -- Mustafa Kemal Univ, Hatay, TURKEYen_US
dc.description.abstractIn this study, the fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. In this study, salt-heavy metal mixtures consisting of 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% UO2, 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% NpO2, and 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO2, UO2, NpO2 and UCO contents was investigated in the structural material of a designed fusion-fission hybrid reactor system. In the designed hybrid reactor system were investigated the effect on the radiation damage of the selected fluid according to each isotopes of structural material in the structural material for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.en_US
dc.description.sponsorshipTurkish Atom Energy Authoren_US
dc.identifier.doi10.1051/epjconf/201612802004
dc.identifier.issn2100-014X
dc.identifier.scopus2-s2.0-85016407424en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.urihttps://doi.org/10.1051/epjconf/201612802004
dc.identifier.urihttps://hdl.handle.net/11616/97764
dc.identifier.volume128en_US
dc.identifier.wosWOS:000389743300009en_US
dc.identifier.wosqualityN/Aen_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherE D P Sciencesen_US
dc.relation.ispartofTheoretical and Experimental Studies in Nuclear Applications and Technology (Tesnat 2016)en_US
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subject3-Dimensional Neutronic Calculationsen_US
dc.subjectStructural Materialen_US
dc.subjectApex Reactoren_US
dc.titleContribution of each isotope in structral material on radiation damage in a hybrid reactoren_US
dc.typeConference Objecten_US

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