Analysis of an ads-fusion hybrid transmutation system using different targets

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dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorCláubia Pereira Bezerra Lima
dc.creatorJose Cassimiro da Silva
dc.date.accessioned2026-01-21T20:56:59Z
dc.date.issued2024-11-23
dc.identifier.doihttps://doi.org/10.29327/9786527209867.959718
dc.identifier.urihttps://hdl.handle.net/1843/1464
dc.languageeng
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofVII SENCIR - Semana Nacional de Engenharia Nuclear e da Energia e Ciências das Radiações
dc.rightsAcesso aberto
dc.rightsCC0 1.0 Universalen
dc.rights.urihttp://creativecommons.org/publicdomain/zero/1.0/
dc.subjectEnergia nuclear
dc.subjectRedução de lixo radioativo
dc.subjectTransmutação nuclear
dc.subjectResíduos radioativos
dc.subjectGestão de lixo nuclear
dc.subject.otherSpallation
dc.subject.otherTransuranic transmutation
dc.subject.otherAccelerator driven system
dc.subject.otherHybrid system
dc.subject.otherNeutron yield
dc.titleAnalysis of an ads-fusion hybrid transmutation system using different targets
dc.typeArtigo de evento
local.citation.epage9
local.citation.issue7
local.citation.spage1
local.description.resumoThis study evaluates the transmutation of nuclear waste in an ADS reactor based on a model proposed by Rubbia and Nifenecker, utilizing different spallation neutron spectra as external sources and reprocessed fuels. The spallation spectra are obtained from a cylindrical target whose geometry was determined in previous studies using a 1 GeV proton beam. The simulated spallation targets are Tungsten (W) and Natural Uranium (U), both solids, as well as Mercury (Hg), Lead (Pb), and Lead-Bismuth Eutectic (LBE) in the liquid state. These fuel assemblies contain an appropriate composition of thorium and reprocessed spent fuels. The JEFF3.3 (Joint Evaluated Fission and Fusion) library, generated for the appropriate temperatures using the NJOY nuclear data processing code, is used for the simulation. The MCNPX 2.6.0 (MCNPX/CINDER) code is employed with the CEM 3.0 (Cascade-Exciton Model) physical model to obtain neutron parameters such as flux at the spallation source surface and the effective multiplication factor (keff). Monteburns 2.0 (MCNP5/ORIGEN 2.1) performs a 600 days burnup. The primary objective of this study is to investigate the possibility of transmuting transuranic from spent fuel when subjected to a neutron flux generated by an ADS reactor with an appropriate composition of reprocessed fuel. The results show the system’s behavior with the different sources obtained coupled to the simulated ADS reactor. The spallation spectrum of the different targets is inserted into the proposed ADS reactor, and variations in the effective k are verified depending on the burning and the contribution of each target to the creation and destruction of actinides. It is verified that minor actinides were reduced for all targets, which resulted in better performance for the reactor with uranium, tungsten, and mercury targets.
local.publisher.countryBrasil
local.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
local.publisher.initialsUFMG
local.subject.cnpqENGENHARIAS::ENGENHARIA NUCLEAR
local.url.externahttps://www.even3.com.br/anais/vii-sencir-semana-nacional-de-engenharia-nuclear-e-da-energia-e-ciencias-das-radiacoes-449507/959718-analysis-of-an-ads-fusion-hybrid-transmutation-system-using-different-targets/

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