The production of 238-242Pu(n,?)239-243Pu fissionable fluids in a fusion-fission hybrid reactor

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:39:39Z
dc.date.available2024-08-04T20:39:39Z
dc.date.issued2014
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, the effect of spent fuel grade plutonium content on Pu259-243 was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, 99-95% Li20Sn80-1-5% SFG-PuO2. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of Pu238-242(n,gamma)Pu239-243 was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0.en_US
dc.identifier.doi10.3139/124.110364
dc.identifier.endpage62en_US
dc.identifier.issn0932-3902
dc.identifier.issue1en_US
dc.identifier.scopus2-s2.0-84898063579en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.startpage58en_US
dc.identifier.urihttps://doi.org/10.3139/124.110364
dc.identifier.urihttps://hdl.handle.net/11616/96407
dc.identifier.volume79en_US
dc.identifier.wosWOS:000334145300008en_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.subjectPower Density Conceptsen_US
dc.subjectApex Reactoren_US
dc.subjectStructural Materialen_US
dc.subjectRadiation-Damageen_US
dc.titleThe production of 238-242Pu(n,?)239-243Pu fissionable fluids in a fusion-fission hybrid reactoren_US
dc.typeArticleen_US

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