Performance Analysis of 233u for Fixed Bed Nuclear Reactors

dc.authorscopusid7102942712
dc.authorscopusid8836601900
dc.authorscopusid35615200600
dc.contributor.authorŞahin,S.
dc.contributor.authorŞahin, Sümer
dc.contributor.authorAcir,A.
dc.contributor.authorŞahin,H.M.
dc.contributor.otherDepartment of Mechanical Engineering
dc.date.accessioned2024-07-05T15:43:33Z
dc.date.available2024-07-05T15:43:33Z
dc.date.issued2010
dc.departmentAtılım Universityen_US
dc.department-tempŞahin S., Department of Mechanical Engineering, Faculty of Engineering, Atilim University, Ankara, 06836 Incek, Gölbaşi, Turkey; Acir A., Faculty of Technology, Gazi University, Turkey; Şahin H.M., Faculty of Technology, Gazi University, Turkeyen_US
dc.description.abstractCriticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel 233UO2/ThO2 as an alternative to low enriched 235UO2 fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as follows: Reactor criticality is already achieved by ∼2% 233UO2 with the mixed 233UO2/ThO2 fuel. At higher 233U fractions, reactor criticality rises rapidly and exceeds keff > 1.5 already by 9% 233UO2. With 100% 233UO 2, start up criticality can reach keff = 2.0975. Time dependent reactor criticality keff and fuel burn up have been investigated for two different mixed fuel 233UO2/ThO 2 compositions, namely: 4 % 233UO2 + 96 % ThO2 for a reactor power of 40 MWel (120 MWth) and 9 % thUO2 + 91 % ThO2 for a reactor power of 70 MWel (210 MWth). Sufficient reactor criticality (keff > 1.06) for continuous operation without fuel change can be sustained during ∼5 and 12 years with 4 % and 9 % 233UO 2 fractions in the mixed fuel, leading to burn ups of ∼36000 and > 105000 MWD/t, respectively. Thorium based fuel produces no prolific uranium. Plutonium production remains negligible. © Carl Hanser Verlag, München.en_US
dc.identifier.citation9
dc.identifier.doi10.3139/124.110097
dc.identifier.endpage247en_US
dc.identifier.issn0932-3902
dc.identifier.issue5en_US
dc.identifier.scopus2-s2.0-77957726039
dc.identifier.startpage243en_US
dc.identifier.urihttps://doi.org/10.3139/124.110097
dc.identifier.urihttps://hdl.handle.net/20.500.14411/3643
dc.identifier.volume75en_US
dc.identifier.wosqualityQ4
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.subject[No Keyword Available]en_US
dc.titlePerformance Analysis of 233u for Fixed Bed Nuclear Reactorsen_US
dc.typeArticleen_US
dspace.entity.typePublication
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