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)

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Agora exibindo 1 - 10 de 10
  • Artigo IPEN-doc 29863
    Manufacturing high-uranium-loaded dispersion fuel plates in Brazil
    2024 - DURAZZO, MICHELANGELO; SOUZA, JOSE A.B.; CARVALHO, ELITA F.U. de; RESTIVO, THOMAZ A.G.; GENEZINI, FREDERICO A.; LEAL NETO, RICARDO M.
    The Nuclear and Energy Research Institute (IPEN-CNEN/SP) has developed and made available for routine production the technology for manufacturing dispersion-type fuel elements for research reactors. However, the fuel produced is limited to a uranium loading of 2.3 gU/cm3 (U3O8) or 3.0 gU/cm3 (U3Si2). To reduce Brazil’s dependence on foreign sources of Mo-99, the Brazilian government plans to construct a new research reactor, the 30 MW open pool Brazilian Multipurpose Reactor (RMB), which will mainly produce domestic Mo-99. Low-enriched uranium fuel will be used in the RMB, and increasing uranium loading will be important to increase the reactor core’s reactivity and fuel life. Uranium loadings of 3.2 gU/cm3 for the U3O8-Al and 4.8 gU/cm3 for the U3Si2-Al are considered the technological limit and have been well demonstrated worldwide. This work aimed to study the manufacturing process of these two highly uranium-loaded dispersion fuels and redefine current procedures. Additionally, UMo-Al dispersion fuel has been extensively studied globally and is likely to be the next commercially available technology. This new fuel utilizes a dispersion of UMo alloy with 7–10 wt% Mo, resulting in a uranium loading between 6 and 8 gU/cm3. We also studied this fuel type for potential use in the RMB research reactor. This work outlines the primary procedures for manufacturing these three types of fuels and the necessary adjustments to IPEN-CNEN/SP current technology. The manufacturing process proved to be well adapted to these new fuels, requiring only minor modifications. A comparison was made of the microstructures of fuel plate meat using three types of uranium compounds. The microstructures of U3Si2-Al and U10Mo-Al dispersions were found to be adequate, while that of U3O8-Al meat deviated significantly from the concept of an ideal dispersion.
  • Artigo IPEN-doc 29094
    Effects of aluminum distearate addition on UO2 sintering and microstructure
    2022 - FREITAS, ARTUR C. de; COSTA, DIOGO R.; JARDIM, PAULA M.; LEAL NETO, RICARDO M.; CARVALHO, ELITA F.U. de; DURAZZO, MICHELANGELO
    Uranium dioxide (UO2) is widely used as a fuel in commercial nuclear light-water reactors (LWRs). Rigorous control of density, pore, and grain size of UO2 pellets are important prerequisites for fuel performance. Solid lubricants, frequently used in pellets manufacturing, minimize structural defects on compaction such as cracks and end-capping, promoting grain growth during sintering. This work presents and discusses the effects of the aluminum distearate (ADS) addition on the sintering behavior and microstructure of UO2 fuel pellets. UO2 and UO2-0.2wt% ADS pellets were sintered at 1760 °C for 5.7 h for comparison purposes. The results show that the densification rate increases using the solid lubricant, but the shrinkage is lowered by 0.7% due to low homogenization. The average grain size was increased by about 35% during sintering. Based on our results and a literature review, a mechanism for grain growth by aluminum addition is proposed.
  • Artigo IPEN-doc 25088
    Sintering behavior of UO2-Er2O3 mixed fuel
    2018 - DURAZZO, MICHELANGELO; FREITAS, ARTUR C.; SANSONE, ALBERTO E.S.; FERREIRA, NILDEMAR A.M.; CARVALHO, ELITA F.U. de; RIELLA, HUMBERTO G.; LEAL NETO, RICARDO M.
    The incorporation of burnable neutron absorbers into nuclear fuel pellets is important regarding reactivity compensation, which enables longer fuel cycles. The dry mechanical blending route is the most attractive process to accomplish absorbers incorporation because of its simplicity. By using this route, the present work has investigated the sintering behavior of UO2Er2O3 mixed fuel. A comparison with UO2Gd2O3 sintering behavior was presented. The behavior of UO2Er2O3 fuel sintering was similar to that reported for UO2Gd2O3 fuel, e.g. two-stage sintering with two peaks in the shrinkage rate curves. The effect showed to be less pronounced for Er2O3. This was attributed to the characteristics of the Er2O3 powder particles used as raw-material, whose agglomerates can be more easily broken and thus better homogenized during the blending with UO2 powder. These results confirmed that sinterability depends directly on the quality of the homogenization of the powders, as seen previously. A second phase was experimentally detected in the UO2Er2O3 system, but its impact on the sintering behavior of this mixed fuel has not yet been clarified.
  • Artigo IPEN-doc 22365
    Fabrication of powder from ductile uranium alloys for use as nuclear dispersion
    2014 - DURAZZO, M.; LEAL NETO, R.M.; ROCHA, C.J.; CARVALHO, E.U. de; RIELLA, H.G.
  • Capítulo IPEN-doc 16640
    Materiais avançados para energia
    2010 - BRESSIANI, JOSE C.; FONSECA, FABIO C.; SERRA, EDUARDO T.; FRAJNDLICH, ELITA U.; SPINACE, ESTEVAM V.; CARVALHO, FATIMA M.S. de; BRAGA, FRANCISCO J.C.; RIELLA, HUMBERTO G.; RAMANATHAN, LALGUDI V.; LEAL NETO, RICARDO M.; BERGAMASCHI, VANDERLEI S.
  • Artigo IPEN-doc 20050
    Investigation of powdering ductile gamma U-10 wt%Mo alloy for dispersion fuels
    2014 - LEAL NETO, R.M.; ROCHA, C.J.; URANO de CARVALHO, E.; RIELLA, H.G.; DURAZZO, M.
  • Artigo IPEN-doc 10998
    Aspectos tecnologicos relacionados aos procedimentos de fabricacao do combustivel UOsub(2)-Gdsub(2)Osub(3)
    2004 - DURAZZO, M.; RIELLA, H.G.; FRAJNDLICH, E.U.C.; LEAL NETO, R.M.
  • Artigo IPEN-doc 10996
    O mecanismo de bloqueio da sinterizacao no sistema UOsub(2)-GDsub(2)Osub(3) - Parte 1: a hipotese da barreira de difusao
    2004 - DURAZZO, M.; RIELLA, H.G.; FRAJNDLICH, E.U.C.; LEAL NETO, R.M.
  • Artigo IPEN-doc 10995
    O mecanismo de bloqueio da sinterizacao no sistema UOsub(2)-GDsub(2)Osub(3) - Parte 2: a ocorrencia do efeito kirkendall
    2004 - DURAZZO, M.; RIELLA, H.G.; FRAJNDLICH, E.U.C.; LEAL NETO, R.M.
  • Artigo IPEN-doc 19901
    The role of Gdsub(2)Osub(3) phase transition on UOsub(2)-Gdsub(2)Osub(3) fuel sintering
    2013 - DURAZZO, MICHELANGELO; LEAL NETO, RICARDO M.; SALIBA SILVA, ADONIS M.; URANO de CARVALHO, ELITA F.; RIELLA, HUMBERTO G.