Investigation of (n,?) reactions in fissionable fluids in a hybrid reactor system

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:39:46Z
dc.date.available2024-08-04T20:39:46Z
dc.date.issued2014
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, the effect of (n,gamma) reactions in spent fuel-grade (SFG)-PuO2, UO2, NpO2 and UCO contents was investigated in a designed hybrid reactor system. In this system, the molten salt-heavy metal mixtures 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2-10% UO2, 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2-10 % NpO2, 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2 10 % UCO were used as fluids. Beryllium (Be) is used as neutron multiplier by (n,2n) reactions. Thence, a Be zone with a width of 3 cm was used in order to contribute on fissile fuel breeding between the liquid first wall and blanket. (n,gamma) reactions were calculated in the liquid first wall, blanket and shield zones, which SFG-PuO2, UO2, NpO2 and UCO contents. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code and nuclear data library ENDF/B-VII.0.en_US
dc.identifier.doi10.3139/124.110410
dc.identifier.endpage208en_US
dc.identifier.issn0932-3902
dc.identifier.issue3en_US
dc.identifier.scopus2-s2.0-84903786959en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.startpage200en_US
dc.identifier.urihttps://doi.org/10.3139/124.110410
dc.identifier.urihttps://hdl.handle.net/11616/96495
dc.identifier.volume79en_US
dc.identifier.wosWOS:000338487300004en_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.subject3-Dimensional Neutronic Calculationsen_US
dc.subjectStructural Materialen_US
dc.subjectApex Reactoren_US
dc.subjectRadiation-Damageen_US
dc.subjectFusionen_US
dc.titleInvestigation of (n,?) reactions in fissionable fluids in a hybrid reactor systemen_US
dc.typeArticleen_US

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