ELITA FONTENELE URANO DE CARVALHO

Resumo

Graduation at Química Industrial from Universidade Federal do Ceará (1978), master's at Nuclear Engineering from Universidade de São Paulo (1992) and doctorate at Nuclear Engineering from Universidade de São Paulo (2004). Has experience in Nuclear Engineering, focusing on Conversion, Enrichment and Manufacture of Nuclear Fuel, acting on the following subjects: combustivel nuclear, fluoreto, tratamento de efluentes, veneno queimavel and meio ambiente. (Text obtained from the Currículo Lattes on October 8th 2021)


Possui graduação em Química Industrial pela Universidade Federal do Ceará (1978), mestrado em Tecnologia Nuclear pela Universidade de São Paulo (1992) e doutorado em Tecnologia Nuclear pela Universidade de São Paulo (2004). Pesquisador do Instituto de Pesquisas Energéticas e Nucleares da Comissão Nacional de Energia Nuclear. Experiência na área de Engenharia de Materiais e Química com ênfase em Conversão, Enriquecimento, Fabricação de Combustível Nuclear, Tratamento de efluentes radioativos e convencionais e reaproveitamento de resíduos industriais e técnicas de caracterização química de materiais. Membro do Instituto Nacional de Tecnologia- INCT para Reatores Nucleares Inovadores. Autor de capítulo de livro intitulado "Radioisotopes: Applications in Physical Sciences, 2011 ISBN: 9789533075105. Título do capítulo: Research Reactor Fuel Fabrication to Produce Radioisotopes. Professor de pós- graduação da Universidade São Paulo nas áreas de caracterização de materiais e de combustível nuclear. Professor visitante na Escola Politécnica da Universidade de São Paulo - modulo I e II de processamento de combustivel nuclear. Bolsista de Produtividade Desen. Tec. e Extensão Inovadora 2 (Texto extraído do Currículo Lattes em 08 out. 2021)

Projetos de Pesquisa
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Resultados de Busca

Agora exibindo 1 - 10 de 13
  • Artigo IPEN-doc 25264
    Study of models for high burn behavior of uranium-7% gadolinium fuel rods for pressurized light water reactors
    2018 - MATTOS, C.E.; SILVA, A.T.E.; MARTINS, I.C.; CARVALHO, E.F.U. de
    The objective of this work is to verify the validity of the results provided by the FRAPCON-3.5 software in the simulation of the behavior of the fuel UO2 - 7% by weight of Gd2O3, in order to evaluate the different models that are being proposed in codes of performance of fuels, in view of the behavior of fuel rods from PWR (Pressurized Water Reactor) under high burning conditions. To perform the analysis of the models that simulate the behavior of fuel pellets, the formation of the microstructure of (UO2-7% Gd2O3), fuel restructuring, temperature in the center of the fuel, comparison of the thermal conductivity between UO2 and the concentration of gadolinium as burnable venom, porosity in the restructured material, release of athermanous fission gases into the restructured material, release of thermally activated fission gases, including gas release models that occur due to grain growth. The results obtained in the computational simulations with the FRAPCON-3.5 program and its comparison with UO2 and UO2-7% Gd2O3, it will be possible to verify that the program has good capacity to predict the operational behavior of PWR fuel rods in permanent regime at high burns under transient condition initialized by reactivity.
  • Artigo IPEN-doc 24939
    Manufacturing low enriched uranium metal by magnesiothermic reduction of UF4
    2018 - DURAZZO, M.; SALIBA-SILVA, A.M.; MARTINS, I.C.; CARVALHO, E.F.U. de; RIELLA, H.G.
    This work presents an experimental description of thermal and physical studies to attain a practical manufacturing process of uranium metal enriched to 20% U235 (LEU–Low Enriched Uranium) by metallothermic reduction of UF4, with nuclear purity, for reduced amounts (1000g of uranium). The magnesiothermic reduction is influenced by the thermal conditions for UF4 reduction. These variables are investigated. The physical arrangement of the crucible/reduction reactor/furnace system and the management of the furnace thermal input in the reduction reactor during the heating were studied. Thermal simulation experiments provided delineation for the reactants’ thermal progress before the ignition of the reaction. The heat input to the reduction system has proved to be the main variable that influenced the efficiency of the process. The levels of metallic yield and reproducibility have been improved. The typical yield in the production of uranium metal was above 80%.
  • Artigo IPEN-doc 23040
    Manufacturing low enriched uranium metal by magnesiothermic reduction of UF4
    2017 - DURAZZO, M.; SALIBA-SILVA, A.M.; MARTINS, I.C.; CARVALHO, E.F.U. de; RIELLA, H.G.
    This work presents an experimental description of thermal and physical studies to attain a practical manufacturing process of uranium metal enriched to 20% U235 (LEU – Low Enriched Uranium) by metallothermic reduction of UF4, with nuclear purity, for reduced amounts (1000 g of uranium) and with radioactive safety. Uranium metal is needed to produce nuclear fuel elements based on uranium silicide (intermetallic U3Si2) and irradiation targets to produce Mo99. This process is a part of Brazilian efforts to fabricate the fuel elements for its research reactors, primarily aiming at the production of radioisotopes for nuclear medicine. The magnesiothermic reduction is influenced by variables which are related to the starting material UF4 and the thermal conditions for its reduction. These variables are investigated. The physical arrangement of the crucible/reduction reactor/furnace system and the management of the furnace thermal input in the reduction reactor during the heating were studied. Thermal simulation experiments provided delineation for the reactants’ thermal progress before the ignition of the metalothermic reaction. The heat input to the reduction system has proved to be the main variable that influenced the efficiency of the process. The levels of metallic yield and reproducibility have been improved, making the production process reproductive and economically viable. The typical yield in the production of uranium metal was above 80%. Unrecovered uranium metal is present in the MgF2 slag and can be recovered at the level of 96% yield. The process of recovering the uranium from the slag is also discussed.
  • Artigo IPEN-doc 15870
    Interdiffusion studies on hot rolled U-10Mo/AA1050
    2010 - SALIBA SILVA, A.M.; MARTINS, I.C.; CARVALHO, E.U.; DURAZZO, M.; RIELLA, H.G.
  • Artigo IPEN-doc 15802
    Studies on hot rolled interdiffucion pair U-10Mo/AA1050
    2010 - SALIBA SILVA, A.M.; MARTINS, I.C.; CARVALHO, E.U.; DURAZZO, M.; RIELLA, H.G.
  • Artigo IPEN-doc 16991
    Uranium briquettes for irradiation target
    2011 - SALIBA SILVA, ADONIS M.; GARCIA, RAFAEL H.L.; MARTINS, ILSON C.; CARVALHO, ELITA F.U. de; DURAZZO, MICHELANGELO
  • Artigo IPEN-doc 14617
    Thermal interdiffusion products of U-10Mo in Al matrix
    2009 - MARTINS, ILSON C.; SORIANO, GUILHERME Z.; DURAZZO, MICHELANGELO; CARVALHO, ELITA F.U. de; MONTAGNA, LEA S.; SALIBA SILVA, ADONIS M.
  • Artigo IPEN-doc 17702
    Nickel electrodeposition over powder compact for irradiation target
    2011 - SALIBA-SILVA, A.M.; GARCIA, R.H.L.; MARTINS, I.C.; URANO de CARVALHO, E.F.; DURAZZO, M.
  • Artigo IPEN-doc 17595
    Metallic uranium production for irradiation target alloys
    2011 - SALIBA SILVA, A.M.; MARTINS, I.C.; SANTOS, L.R. dos; SILVA, D.G. da; CARVALHO, E.F.U. de; RIELLA, H.G.; DURAZZO, M.
  • Artigo IPEN-doc 15191
    Studies on U-Mo interdiffusion in Al-matriz
    2009 - MARTINS, ILSON C.; SORIANO, GUILHERME Z.; CARVALHO, ELITA F.U. de; DURAZZO, MICHELANGELO; MONTAGNA, LEA S.; SALIBA SILVA, ADONIS M.