Neutronic examination of the U-Mo accident tolerant fuel for VVER-1200 reactors

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dc.authoridDAYDAS, SEMRA/0000-0003-3323-4092
dc.contributor.authorDaydas, Semra
dc.contributor.authorTiftikci, Ali
dc.date.accessioned2025-03-23T19:39:12Z
dc.date.available2025-03-23T19:39:12Z
dc.date.issued2024
dc.departmentSinop Üniversitesi
dc.description.abstractIn this study, we investigated the possibility of employing accident tolerant fuel (ATF) in VVER-1200/V491 assembly without gadolinium-containing fuel rods using the Monte Carlo code Serpent 1.1.7 with ENDF/B-VII cross-section library. The analysis involves assembly design with reflective boundary conditions. To compare the neutronic performances, U-5Mo, U-7.5Mo, U-10Mo, and U-15Mo fuels were chosen in addition to ordinary UO2 2 fuel. The concentration of 135 Xe, 149 Sm, fissile and fertile isotopes with burnup, reactivity feedback with fuel temperature variation, and beta eff values were calculated. The results indicate that the fuel cycle length increases by 54.27% for U-5Mo, 32.6% for U-7.5Mo, and 13.8% for U-10Mo, while it decreases by 16.4% for U-15Mo fuel. Additionally, the effect of 95 Mo content in natural Mo was investigated by reducing the 95 Mo concentration. According to the results, each proposed fuel's fuel cycle length extended when the depletion ratio of 95 Mo increased. Additionally, the calculations for reactivity feedback guarantee safe operating conditions for all UxMo fuels.
dc.identifier.doi10.1016/j.net.2024.02.021
dc.identifier.endpage2632
dc.identifier.issn1738-5733
dc.identifier.issue7
dc.identifier.scopus2-s2.0-85185604283
dc.identifier.scopusqualityQ1
dc.identifier.startpage2625
dc.identifier.urihttps://doi.org/10.1016/j.net.2024.02.021
dc.identifier.urihttps://hdl.handle.net/11486/6285
dc.identifier.volume56
dc.identifier.wosWOS:001299007800001
dc.identifier.wosqualityQ1
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherKorean Nuclear Soc
dc.relation.ispartofNuclear Engineering and Technology
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/openAccess
dc.snmzKA_WOS_20250323
dc.subjectVVER-1200
dc.subjectAccident-tolerant fuel (ATF)
dc.subjectU-Mo
dc.subjectSerpent
dc.subjectDepleted Mo
dc.subjectFeCrAl
dc.subjectNiobium
dc.titleNeutronic examination of the U-Mo accident tolerant fuel for VVER-1200 reactors
dc.typeArticle

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