Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison

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dc.creatorRochkhudson Batista de Faria
dc.creatorFelipe Martins Gomes Pereira
dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorFabiano Cardoso da Silva
dc.creatorAngela Fortini Macedo Ferreira
dc.creatorClaubia Pereira Bezerra Lima
dc.date.accessioned2023-07-24T19:15:37Z
dc.date.accessioned2025-09-08T23:51:03Z
dc.date.available2023-07-24T19:15:37Z
dc.date.issued2017
dc.identifier.doihttps://doi.org/10.15392/bjrs.v7i2B.769
dc.identifier.issn2319-0612
dc.identifier.urihttps://hdl.handle.net/1843/56884
dc.languagepor
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofNuclear Energy for National Projects
dc.rightsAcesso Aberto
dc.subjectAnálise por ativação nuclear
dc.subjectCombustiveis
dc.subject.otherNeutronic analysis
dc.subject.otherFuel element
dc.subject.otherBurnable poison
dc.titleNeutronic analysis of a fuel element with variations in fuel enrichment and burnable poison
dc.typeArtigo de evento
local.citation.epage13
local.citation.issueEighth International Nuclear Atlantic Conference 2017 (INAC 2017)
local.citation.spage1
local.description.resumoIn this work, the goal was to evaluate the neutronic behavior during the fuel burnup changing the amount of burnable poison and fuel enrichment. The analyses used a 17 x 17 PWR fuel element, simulated using the 238 groups library cross-section collapsed from ENDF/BVII.0 and TRITON module of SCALE 6.0 code system. The results confirmed the effective action of the burnable poison in the criticality control, especially at Beginning Of Cycle (BOC) and in the burnup kinetics, because at the end of the fuel cycle there was a minimal residual amount of neutron absorbers (155Gd and 157Gd), as expected, showing the burnup of the Gd in the simulation methodology adopted. Furthermore, the results show that increasing the Gd insertion percentage does not change its final residual amount. At the end of the cycle, the fuel element was still critical for all the simulated situations, which indicates the possibility of extending the fuel burnup.
local.identifier.orcidhttps://orcid.org/0000-0003-0264-9148
local.identifier.orcidhttps://orcid.org/0000-0002-2960-3150
local.identifier.orcidhttps://orcid.org/0000-0002-5262-657X
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://www.bjrs.org.br/revista/index.php/REVISTA/article/view/769

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