Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:41:19Z
dc.date.available2024-08-04T20:41:19Z
dc.date.issued2015
dc.departmentİnönü Üniversitesien_US
dc.descriptionInternational Conference on Computational and Experimental Science and Engineering (ICCESEN) -- OCT 25-29, 2014 -- Antalya, TURKEYen_US
dc.description.abstractIn this study, the effect of the radiation damage of spent fuel-grade plutonium content was investigated in the structural material of a designed fusion-fission hybrid reactor system. In this study, the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, and 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. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In this study, damage to the total structural material and each 1.0 cm thickness thereof was measured as a function of radiation energy, using the selected fluid rates, 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.identifier.doi10.12693/APhysPolA.128.B-113
dc.identifier.endpageB117en_US
dc.identifier.issn0587-4246
dc.identifier.issn1898-794X
dc.identifier.issue2Ben_US
dc.identifier.scopus2-s2.0-84947722619en_US
dc.identifier.scopusqualityQ4en_US
dc.identifier.startpageB113en_US
dc.identifier.urihttps://doi.org/10.12693/APhysPolA.128.B-113
dc.identifier.urihttps://hdl.handle.net/11616/97060
dc.identifier.volume128en_US
dc.identifier.wosWOS:000363011700031en_US
dc.identifier.wosqualityQ4en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherPolish Acad Sciences Inst Physicsen_US
dc.relation.ispartofActa Physica Polonica Aen_US
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subject3-Dimensional Neutronic Calculationsen_US
dc.subjectBreeder Apex Reactoren_US
dc.subjectFusion Breederen_US
dc.subjectHylife-Iien_US
dc.subjectDamageen_US
dc.titleFluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Codeen_US
dc.typeConference Objecten_US

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