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Physical Aspects of the Waste of Re-Enrichment Utilization for Recycled Uranium from VVER-1000/1200 Spent Fuel Reprocessing in Molten Salt Reactors

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dc.contributor.authorFeynberg, O. S.
dc.contributor.authorIgnatyev, S. V.
dc.contributor.authorKotov, Y. A.
dc.contributor.authorNevinitsa, V. A.
dc.contributor.authorSmirnov, A. Y.
dc.contributor.authorСмирнов, Андрей Юрьевич
dc.date.accessioned2024-11-30T01:41:59Z
dc.date.available2024-11-30T01:41:59Z
dc.date.issued2021
dc.description.abstractThe problems of utilization of waste from re-enrichment of regenerated uranium from U-232 isotope in a reactor with circulating liquid fuel based on melts of metal fluoride salts are discussed. The effect of isotopic composition of the purification cascade selection fraction on the spectrum and reactivity coefficients in a liquid salt nuclear reactor depending on the content of U-235 isotope is studied. It is shown that compositions with a high content of U-235 isotope, on one hand, are more promising, since less minor actinides are produced owing to the low content of U-238 isotope, and on the other hand, more favorable reactivity effects are provided with moderate enrichment of U-235 isotope.
dc.format.extentС. 1495-1499
dc.identifier.citationPhysical Aspects of the Waste of Re-Enrichment Utilization for Recycled Uranium from VVER-1000/1200 Spent Fuel Reprocessing in Molten Salt Reactors / Feynberg, OS [et al.] // Physics of Atomic Nuclei. - 2021. - 84. - № 8. - P. 1495-1499. - 10.1134/S106377882108007X
dc.identifier.doi10.1134/S106377882108007X
dc.identifier.urihttps://www.doi.org/10.1134/S106377882108007X
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dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/25206
dc.relation.ispartofPhysics of Atomic Nuclei
dc.titlePhysical Aspects of the Waste of Re-Enrichment Utilization for Recycled Uranium from VVER-1000/1200 Spent Fuel Reprocessing in Molten Salt Reactors
dc.typeArticle
dspace.entity.typePublication
oaire.citation.issue8
oaire.citation.volume84
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