Neutronic study of ThF4-UF4-LiF fuel mixture in the molten salt hybrid reactor for 233U denaturing

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dc.contributor.authorSahin, Haci Mehmet
dc.contributor.authorSahin, Sumer
dc.contributor.authorTunc, Guven
dc.contributor.authorSahinen, Huseyin
dc.date.accessioned2026-04-25T14:20:01Z
dc.date.available2026-04-25T14:20:01Z
dc.date.issued2026
dc.departmentSinop Üniversitesi
dc.description.abstractThis study investigates a fusion-fission hybrid reactor concept using a thorium-based molten salt fuel mixture to enhance proliferation resistance and operational sustainability. Neutron transport and reaction rates were modeled using the Monte Carlo N-particle code (MCNP6) with ENDF/B-VIII.0 data. Thorium is mixed homogeneously with 2.25 % depleted uranium (DU) in order to denaturate the 233U fuel. The analysis. showed that with 75 % 6Li enrichment and a 50 cm coolant layer, the tritium breeding ratio (TBR) remained above 1.05 for a period of four years. The energy multiplication factor (M) increased from 1.88 to 2.2, consistently exceeding the minimum target of 1.5. Under the hard fusion neutron flux, more than 96 % of the plutonium produced was 239Pu, heavier plutonium isotopes were burnt in situ. The production of the low enriched 233U fuel increased to about 12 % after 34 months. These results indicate the technical feasibility of a thorium-based fusion-fission hybrid reactor with improved proliferation resistance, efficient energy multiplication, and sustainable fuel cycle characteristics.
dc.identifier.doi10.1016/j.pnucene.2026.106237
dc.identifier.issn0149-1970
dc.identifier.issn1878-4224
dc.identifier.orcid0000-0001-7038-8168
dc.identifier.scopus2-s2.0-105030452258
dc.identifier.scopusqualityQ1
dc.identifier.urihttps://doi.org/10.1016/j.pnucene.2026.106237
dc.identifier.urihttps://hdl.handle.net/11486/8322
dc.identifier.volume193
dc.identifier.wosWOS:001662357500001
dc.identifier.wosqualityQ1
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherPergamon-Elsevier Science Ltd
dc.relation.ispartofProgress in Nuclear Energy
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.snmzKA_WOS_20260420
dc.subjectFusion-fission hybrid
dc.subjectMolten salt
dc.subjectThorium fuel
dc.subjectDepleted uranium
dc.subjectNickel alloy
dc.subjectRadiation damage
dc.titleNeutronic study of ThF4-UF4-LiF fuel mixture in the molten salt hybrid reactor for 233U denaturing
dc.typeArticle

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