Design studies for A 50 MWth molten salt fast reactor

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dc.authoridTUNC, GUVEN/0000-0001-7038-8168
dc.authoridSahiner, Huseyin/0000-0002-3191-1590
dc.contributor.authorSahin, Sumer
dc.contributor.authorSahin, Haci Mehmet
dc.contributor.authorTunc, Guven
dc.contributor.authorSahiner, Huseyin
dc.date.accessioned2025-03-23T19:38:22Z
dc.date.available2025-03-23T19:38:22Z
dc.date.issued2023
dc.departmentSinop Üniversitesi
dc.description.abstractIn this paper, design studies for a 50 MWth Molten Salt Reactor (MSR) have been carried out for the eutectic point of the molten salt mixture. Neutronic calculations are performed with the 19.75% enriched uranium and 100% 7Li isotope contained. The MCNP6 nuclear code was used with the ENDF/B-VIII nuclear data library to determine geometry dimensions and criticality. The time-evolution of Pu and other heavy isotopes in the reactor are calculated with the interface code MCNPAS. Four models are investigated with different reactor vessel materials: Model 1: Ni alloy (NiCrW-Hastelloy steel), Model 2: Beryllium, Model 3: Graphite and Model 4: Silicon Carbide (SiC). For the respective models, time-dependent criticality calculations are performed with a startup criticality value of keff =1.0262, 1.0298, 1.0404, and 1.0223. The 235U consumed for the corresponding models over the 10 years of reactor operation are 257.9 kg, 258.8 kg, 259.4 kg and 257.9 kg, respectively. At the same time, the 238U consumptions are 400.6 kg, 380.0 kg, 379.8 kg, and 400.9 kg, respectively. The amount of the higher quality new fuel (239Pu) produced for 10 years is calculated as 129.10 kg, 127.41 kg, 122.95 kg and 128.66 kg, for the respected models.
dc.identifier.doi10.1016/j.pnucene.2023.104964
dc.identifier.issn0149-1970
dc.identifier.issn1878-4224
dc.identifier.scopus2-s2.0-85177846750
dc.identifier.scopusqualityQ1
dc.identifier.urihttps://doi.org/10.1016/j.pnucene.2023.104964
dc.identifier.urihttps://hdl.handle.net/11486/6136
dc.identifier.volume166
dc.identifier.wosWOS:001127555000001
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_20250323
dc.subjectMSR
dc.subjectSMR
dc.subjectFast reactor
dc.subjectMolten salt-fuel mixture
dc.subjectLiquid fuel
dc.titleDesign studies for A 50 MWth molten salt fast reactor
dc.typeArticle

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