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Preliminary performance evaluation of an LEU+ based dual-cooled duplex UO2-ThO2 fuel for advanced PWR assembly

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creativeworkseries.issn2452-3038
dc.contributor.authorRifai. H.
dc.contributor.authorKabach, O.
dc.contributor.authorChakir, E. M.
dc.contributor.authorSadoune, Z.
dc.date.accessioned2025-11-26T11:51:16Z
dc.date.available2025-11-26T11:51:16Z
dc.date.issued2025
dc.description.abstractThis study presents a comprehensive neutronic analysis of dual-cooled annular duplex fuel assemblies incorporating UO2-ThO2 composition for application in advanced pressurized water reactors (PWRs). The investigation employs a 13 × 13 fuel assembly configuration to evaluate the operational enhancement potential of modern reactor systems. The research methodology focuses on the comparative assessment of burnup characteristics across varying uranium enrichment levels, benchmarking the neutronic performance of dual-cooled duplex fuel against conventional solid 17 × 17 and dual-cooled 13 × 13 UO2 assemblies. The results demonstrate that the proposed UO2-ThO2 dual-cooled duplex fuel configuration with 7 wt.% U-235 achieves discharge burnup equivalent to that of conventional solid UO2 assemblies. Safety analysis encompasses the quantification of plutonium isotope production and minor actinide generation, revealing that dual-cooled duplex assemblies produce significantly reduced quantities of plutonium isotopes and lower concentrations of minor actinides, including neptunium (Np), americium (Am), and curium (Cm), relative to conventional all-UO₂ assemblies. Reactivity coefficient analysis confirms that both the fuel temperature coefficient (FTC) and moderator temperature coefficient (MTC) maintain consistently negative values throughout the operational cycle. These coefficients not only satisfy but exceed the established safety criteria for PWR operations, thereby demonstrating the enhanced safety margins and operational performance characteristics inherent to the dual-cooled duplex fuel assembly design.
dc.description.urihttps://nucet.pensoft.net/article/163189/list/8/
dc.identifier.citationRifai H, Kabach O, Chakir EM, Sadoune Z (2025) Preliminary performance evaluation of an LEU+ based dual-cooled duplex UO2-ThO2 fuel for advanced PWR assembly. Nuclear Energy and Technology 11(3): 195–208. https://doi.org/10.3897/nucet.11.163189
dc.identifier.doi10.3897/nucet.11.163189
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/39852
dc.publisherНИЯУ МИФИ
dc.subjectAP1000 Assembly
dc.subjectSafety Parameters
dc.subjectNeutronic Performance
dc.subjectDual-Cooled Duplex Fuel
dc.titlePreliminary performance evaluation of an LEU+ based dual-cooled duplex UO2-ThO2 fuel for advanced PWR assembly
dc.title.alternativeНАУЧНЫЕ СТАТЬИ
dc.typeArticleru
dspace.entity.typePublication
journal.titleNuclear Energy and Technology (NUCET)
journalvolume.identifier.nameNuclear Energy and Technology (NUCET)
relation.isJournalIssueOfPublication591801e9-ddf7-49d8-afdf-c87b3e8faac9
relation.isJournalIssueOfPublication.latestForDiscovery591801e9-ddf7-49d8-afdf-c87b3e8faac9
relation.isJournalOfPublicatione11ecc6c-1851-485a-af73-18119b4fce7f
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