Neutronic evaluation of transuranics in a GFR model using MCNPX and scale 6.0

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dc.creatorAnderson a. p. Macedo
dc.creatorVictor Faria de Castro
dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorFabiano Cardoso
dc.creatorClarysson A. M. da Silva
dc.creatorClaubia Pereira
dc.date.accessioned2025-02-14T20:02:40Z
dc.date.accessioned2025-09-08T23:37:24Z
dc.date.available2025-02-14T20:02:40Z
dc.date.issued2017
dc.format.mimetypepdf
dc.identifier.urihttps://hdl.handle.net/1843/80099
dc.languageeng
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofInternational Nuclear Atlantic Conference
dc.rightsAcesso Aberto
dc.subjectUrânio
dc.subjectCombustíveis nucleares
dc.subjectReatores nucleares
dc.subject.otherCoefficient of reactivity
dc.subject.otherNuclear fuel
dc.subject.otherNuclear reactors
dc.titleNeutronic evaluation of transuranics in a GFR model using MCNPX and scale 6.0
dc.typeArtigo de evento
local.citation.epage10
local.citation.spage1
local.description.resumoIn this study, a GFR core model with 100 MWt was evaluated using three different fuel compositions: a conventional (U, Pu)C and two reprocessed fuels reprocessed by UREX+ technique one spiked with depleted uranium, (U,TRU)C, and the other one reprocessed spiked with thorium, (Th,TRU)C. The reprocessed fuel came from a PWR standard fuel (33,000 MWd/T burned) with 3.1% of initial enrichment and left in the pool by 5 years. Some important nuclides were followed during burnup and kinf was evaluated for 1400 days. The results also include analysis of the B4C insertion and the temperature coefficient. The simulations were performed comparing results between MCNPX and SCALE 6.0 codes. The main goal is to validate the model and evaluate the possibility to use TRU spiked with Th in a GFR.
local.identifier.orcidhttps://orcid.org/0000-0002-2960-3150
local.identifier.orcidhttps://orcid.org/0000-0002-3082-644X
local.identifier.orcidhttps://orcid.org/0000-0001-5999-9961
local.publisher.countryBrasil
local.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
local.publisher.initialsUFMG
local.url.externahttps://inis.iaea.org/records/r9jhr-s3736

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