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Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study

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creativeworkseries.issn2452-3038
dc.contributor.authorBanni, F. E.
dc.contributor.authorGogon, B. L.
dc.contributor.authorKabach, O.
dc.contributor.authorChakir, E. M.
dc.date.accessioned2024-09-19T12:51:22Z
dc.date.available2024-09-19T12:51:22Z
dc.date.issued2024
dc.description.abstractThis article investigates alternate fuel options for Pressurized Water Reactors (PWRs), focusing on thorium use to address safety, efficiency, and waste issues associated with standard UO2 fuel. Challenges in thorium utilization, such as the lack of a fissile isotope, are handled using approaches such as homogeneous mixtures and heterogeneous arrangements, promoting the exploration of (Th-233U-235U)O2 fuel in various assembly configurations. According to recent research, the annular dual-cooled assembly design has promising results in terms of fuel efficiency and safety while lowering the requirement for higher fissile enrichment levels. Studies additionally demonstrate that annular dual-cooled duplex fuel configurations can produce higher discharge burnup and lower power peaking factors than traditional UO2 fuel. The purpose of this work is to analyze and compare the performance of (Th-233U-235U)O2 fuel in various configurations against conventional UO2 fuel, focusing on key characteristics such as reactivity change, criticality, discharge burnups, and reactivity feedback coefficients.
dc.identifier.citationEl Banni F, Gogon BLH, Kabach O, Chakir EM (2024) Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study. Nuclear Energy and Technology 10(3): 169-178. https://doi.org/10.3897/nucet.10.125376
dc.identifier.doi10.3897/nucet.10.125376
dc.identifier.issn2452-3038
dc.identifier.urihttps://nucet.pensoft.net/article/125376/list/9/
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/14973
dc.relation.ispartofNuclear Energy and Technology
dc.subjectPWR
dc.subjectDual-cooled annular assembly
dc.subjectNeutronic evaluation
dc.subjectCriticality
dc.subjectSafety coefficients
dc.subjectThorium-based nuclear fuel
dc.titleAnalyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study
dc.typejournal-article
dspace.entity.typePublication
oaire.citation.issue3
oaire.citation.volume10
relation.isJournalIssueOfPublication4aca891f-6a8b-4437-9f27-4ee5e609e53f
relation.isJournalIssueOfPublication.latestForDiscovery4aca891f-6a8b-4437-9f27-4ee5e609e53f
relation.isJournalOfPublicatione11ecc6c-1851-485a-af73-18119b4fce7f
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