Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening

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dc.contributor.authorYapici, H
dc.contributor.authorBayrak, M
dc.date.accessioned2019-08-01T13:38:39Z
dc.date.available2019-08-01T13:38:39Z
dc.date.issued2005
dc.departmentNiğde ÖHÜ
dc.description.abstractThe purpose of this study is to denature nuclear weapon grade quality plutonium in a thorium fusion breeder. Ten fuel rods containing the mixture of ThO2 and PuO2 are placed in a radial direction in the fissile zone where ThO2 is mixed with variable amounts of PuO2 to obtain a quasi-constant nuclear heat production density. The plutonium composition volume fractions in the fuel rods are gradually increased from 0.1 % to 1 % by 0.1 % increments. The fissile fuel zone is cooled with four various coolants with a volume fraction ratio of 1 (V-coolant/V-fuel = 1). These coolants are helium gas, flibe "Li2BeF4". natural lithium and eutectic lithium "Li-17Pb83". Nuclear weapon grade quality (239)pU in the fuel composition is denatured due to the accumulation of the (240)pU isotope in the fissile zone after IS months of plant operations. Under a first wall fusion neutron. current load of 2.222 x 10(14) (14.1 MeV n/cm(2)s), which corresponds to 5 MW/m(2) by a plant factor of 100 %, at the end of the plant operation, the fissile fuel enrichment quality between 6.0 % and 10 % is obtained depending on the coolant types. During the plant operation, the tritium breeding ratio (TBR) should be at least 1.05. In the selected blanket, only the flibe coolant is already self sustaining at start up. The TBR increases steadily due to the higher neutron multiplication rate during the plant operation period. The highest TBR is obtained for the eutectic lithium coolant 1.4035, followed by the flibe coolant 1.3095, helium gas coolant 1.2172 and natural lithium coolant 1.0551 at the end of the operation period of 48 months. The energy multiplication factor M changed between 2.17331 and 6.6241 depending on coolant type during the operation period. The peak to average fission power density ratio F in the blanket decreases by similar to 15 %, which allows a more uniform power generation in the fissile zone. The isotopic percentage of Pu-240 reaches higher than 5 % in all coolant types. This is very important for international safety. (C) 2004 Elsevier Ltd. All rights reserved.
dc.identifier.doi10.1016/j.enconman.2004.06.031
dc.identifier.endpage1228
dc.identifier.issn0196-8904
dc.identifier.issue45511
dc.identifier.scopus2-s2.0-10844270400
dc.identifier.scopusqualityQ1
dc.identifier.startpage1209
dc.identifier.urihttps://dx.doi.org/10.1016/j.enconman.2004.06.031
dc.identifier.urihttps://hdl.handle.net/11480/5596
dc.identifier.volume46
dc.identifier.wosWOS:000226507400015
dc.identifier.wosqualityQ1
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.institutionauthor[0-Belirlenecek]
dc.language.isoen
dc.publisherPERGAMON-ELSEVIER SCIENCE LTD
dc.relation.ispartofENERGY CONVERSION AND MANAGEMENT
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.subjecthybrid reactor
dc.subjectpower flattening
dc.subjectdenaturation
dc.subjectplutonium
dc.subjectthorium
dc.titleNeutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening
dc.typeArticle

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