Transmutation of Minor Actinides in Candu Reactors

dc.authorscopusid 7102942712
dc.authorscopusid 35615200600
dc.authorscopusid 8836601900
dc.authorscopusid 6602136205
dc.contributor.author Şahin,S.
dc.contributor.author Şahin,H.M.
dc.contributor.author Acir,A.
dc.contributor.author Al-Kusayer,T.A.
dc.contributor.other Department of Mechanical Engineering
dc.date.accessioned 2024-07-05T15:43:32Z
dc.date.available 2024-07-05T15:43:32Z
dc.date.issued 2010
dc.department Atılım University en_US
dc.department-temp Şahin S., Atilim University, Faculty of Engineering, Ankara, Turkey; Şahin H.M., Faculty of Technology, Beşevler, Ankara, Turkey; Acir A., Faculty of Technology, Gazi University, Beşevler, Ankara, Turkey; Al-Kusayer T.A., College of Engineering, King Saud University, Riyadh, Saudi Arabia en_US
dc.description.abstract Large quantities of nuclear waste plutonium have been accumulated in the civilian LWRs and CANDU reactors in form of minor actinides (MAs). Reactor grade plutonium and other transuranium elements can be used as a booster fissile fuel material in form of mixed ThO2/MAO2 fuel in a CANDU fuel bundle in order to assure reactor criticality. Following fuel compositions have been selected for investigations; Reactor grade plutonium: Circled digit one 96 % thoria (ThO2) + 4 % PuO2 and Circled digit two 91 % ThO2 + 5 % UO2 + 4 % PuO2. The latter is used for the purpose of denaturing the new 233U fuel with 238U. The behavior of the criticality k∞ and the burn-up values of the reactor have been pursued by full power operation for > ∼ 8 years. The reactor starts with k∞ = ∼ 1.39 and the criticality drops down asymptotically to values k∞ > 1.06, still acceptable and useable in a CANDU reactor. Reactor criticality k ∞ remains nearly constant between the 4th year and 7th year of plant operation and then a slight increase is observed thereafter, along with a continuous depletion of thorium fuel. Totality of nuclear waste actinides after the extraction of uranium isotopes: The best fuel compositions with respect to power flattening as well as long term reactivity have been found by mixing thoria with 14 % minor actinides in form of MAO 2 in the central fuel bundle and decreasing the MAO2 content in radial direction at discrete levels down to 2 % at the periphery. The temporal variation of the criticality k∞ and the burn-up values of the reactor have been calculated for a period of 10 years, operated at full power. The criticality starts at time zero near to k∞ = ∼ 1.24 for both fuel compositions. A sharp decrease of the criticality has been observed during the first year as a consequence of rapid plutonium burnout in the actinide fuel. The criticality becomes quasi constant after the 2 nd year after sufficient 233U is accumulated and remains close to k∞,end = ∼1.06 over ∼ 10 years. Quasi-uniform power generation density has been realized in the fuel bundle throughout the reactor operation. In all investigated cases, plutonium burns up rapidly and after the 2nd year, the CANDU reactor begins to operate practically as a thorium burner. en_US
dc.identifier.citationcount 0
dc.identifier.doi 10.1109/INREC.2010.5462555
dc.identifier.isbn 978-142445214-9
dc.identifier.scopus 2-s2.0-77953256136
dc.identifier.uri https://doi.org/10.1109/INREC.2010.5462555
dc.identifier.uri https://hdl.handle.net/20.500.14411/3641
dc.institutionauthor Şahin, Sümer
dc.language.iso en en_US
dc.relation.ispartof 2010 1st International Nuclear and Renewable Energy Conference, INREC'10 -- 2010 1st International Nuclear and Renewable Energy 2010 1st International Nuclear and Renewable Energy Conference, INREC'10 -- 21 March 2010 through 24 March 2010 -- Amman -- 80564 en_US
dc.relation.publicationcategory Konferans Öğesi - Uluslararası - Kurum Öğretim Elemanı en_US
dc.rights info:eu-repo/semantics/closedAccess en_US
dc.scopus.citedbyCount 0
dc.subject [No Keyword Available] en_US
dc.title Transmutation of Minor Actinides in Candu Reactors en_US
dc.type Conference Object en_US
dspace.entity.type Publication
relation.isAuthorOfPublication 565a82c2-51d6-4b83-98c0-f1bcbae75db9
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relation.isOrgUnitOfPublication.latestForDiscovery f77120c2-230c-4f07-9aae-94376b6c4cbb

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