ELITA FONTENELE URANO DE CARVALHO

ELITA FONTENELE URANO DE CARVALHO

(Fonte: Lattes)

ORCID

ScopusID

ResearcherID

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)

Página do item completo

Resultados de Busca

Agora exibindo 1 - 10 de 170

Polymeric membranes grafted by ionizing radiation for uranium adsorption
2024 - CARDOSO, A.C.P.; GARCIA, R.H.L.; CARVALHO, E.F.U.; AL SHEIKHLY, M.; KODAMA, Y.
Fuel elements production by IPEN-CNEN has a perspective to be increased to attend Brazilian Multipurpose Reactor, under construction. This production generates liquid waste that requires proper treatment to minimize environmental impacts, promoting more sustainable practices. Considering the rise on nuclear power energy generation, and that there is global lack of terrestrial uranium sources, the increasing demand for this element has been leading to uranium exploit alternatives. So, several researches are available on uranium adsorption from sea water. Adsorption is one of process for removing metals from wastewater, due to its high selectivity and low environmental impact. Taking into account this scenary, in this study, Winged Polypropylene (WPP) fabric was grafted via ionizing radiation (RIG) with the monomer Bis[2-(methacryloyloxy) ethyl] phosphate (B2MP). RIG promotes functionalization of WPP with phosphate groups that are prone to capture U from solution. Synthesized WPP-g-polyB2MP membranes were characterized by Scanning electron microscopy (SEM), Raman spectroscopy, thermogravimetry and, uranium adsorption capacity by ICP-OES and gamma spectrometry. WPP-g-polyB2MP membranes were successfully synthesized by ionizing radiation grafting direct method. Reaction parameters, like reactants concentration, radiation absorbed dose, affected the degree of grafting (DoG). By physico-chemical characterization results it was possible to observe DoG differences with parameters variation. Optimization of these parameters was sought in order to achieve uranium adsorption, and to increase the adsorption capacity of the membrane.
Overcoming FMEA shortcomings
2024 - IBARRA, LUIS A.C.; CARVALHO, ELITA F.U. de; DURAZZO, MICHELANGELO
Development of a FMEA method to reduce ambiguity in criteria and provide a more time-effective way of applying it, without creating complicated and complex additional criteria or bureaucracy. Using Design Science for the proposal and testing of a new FMEA tool in a specific industrial process context. The proposed method minimized time needed for the analysis, simplified documentation, and minimized ambiguities in risk criteria. The proposed tool has been evaluated in only one company and no structured feedback from users has been taken. The proposed method can be applied to make FMEA analysis more effective and less time-consuming. The proposed method has been created during the research process and addresses some of the FMEA's shortcomings that are frequently remarked by literature in an innovative way.
A novel automated thickness measurement method and device for nuclear fuel plates
2024 - KOBAYOSHI, MARCELO; LEAL NETO, RICARDO M.; CARVALHO, ELITA F.U. de; RESTIVO, THOMAZ A.G.; DURAZZO, MICHELANGELO
The Nuclear and Energy Research Institute (IPEN-CNEN/SP) currently employs manual external u-shape frame micrometers with non-rotating spindles, and chamfered measuring anvils at 21 pre-defined points to control the thickness of its fuel plates. However, it is acknowledged that this method introduces the human element into the measurement process, potentially compromising result accuracy and the integrity of the fuel plates' surfaces. This research introduces a novel thickness measurement method and an accompanying automated device featuring precise movement mechanisms, data capture, transcription, and processing. Our findings emphasize the effectiveness of this new measurement system and the structural integrity of the equipment, highlighting its potential to significantly enhance both the speed and metrological reliability of dimensional control processes for nuclear fuel plates manufactured at IPEN-CNEN/SP.
Polymeric membranes grafted by ionizing radiation for uranium adsorption
2024 - CARDOSO, A.; GARCIA, R.L.; CARVALHO, E.F.U. de; AL SHEIKHLY, M.; KODAMA, Y.
Radiation Induced Graft polymerization (RIG) of B2MP onto nylon fabric for uranium adsorption
2024 - CARDOSO, A.C.P.; GARCIA, R.H.L.; CARVALHO, E.F.U. de; AL SHEIKHLY, M.; KODAMA, Y.
A purification process for the tetrauranium fluoride effluent
2024 - GARCIA, R.H.L.; KODAMA, Y.; CARVALHO, E.F.U.; RIELLA, H.G.; SCHAFFER, D.; CONTURBIA, G.C.
Fragmentation of fuel particles in rolling U3Si2-Al dispersion fuel plates
2024 - DURRAZO, MICHELANGELO; MARCONDES, GILBERTO H.; CARVALHO, ELITA F.U. de; BARROS, GUILHERME D. de; LEAL NETO, RICARDO M.
The Nuclear and Energy Research Institute (IPEN-CNEN/SP) has recently developed a process to produce the nuclear fuel required to run the Brazilian Multipurpose Reactor (RMB), using U3Si2-Al dispersion in plate-type fuel elements. Since the late 1980s, regular production of dispersion-based fuel plates has kept the maximum fines content (<44 μm) of 20 wt%. However, IPEN’s U3Si2 powder manufacturing process typically generates fines between 25 and 30 wt%, making it necessary to discard and recycle about 5 to 10 wt% of the powder during manufacturing. The severe fines requirements necessitate careful comminution with multiple intermediate screening steps, which has a negative impact on RMB’s fuel production scalability (60 elements per year). To improve the current fines content specification for the powder, this study focuses on looking into U3Si2 particle fragmentation during fuel plate manufacturing. Quantitative microscopy methods and image analysis were employed. The findings revealed a significant increase in fines content during the rolling process, with levels reaching up to 59 wt%. Hence, to ensure high-quality dispersion, it becomes crucial to specify the fines content in the fuel plate obtained after rolling rather than just in the original powder. The results recommend that a new U3Si2 powder specification could allow a maximum fine content of 30 wt%. More research is ongoing to confirm this recommendation.
Automated thickness measurement system for nuclear fuel plates
2024 - KOBAYOSHI, MARCELO; LEAL NETO, RICARDO M.; CARVALHO, ELITA F.U. de; DURAZZO, MICHELANGELO
Thickness measurements of nuclear fuel plates manufactured at the Nuclear Fuel Center of the Nuclear and Energy Research Institute (IPEN-CNEN/SP) are currently performed using manual external U-shaped frame micrometers with non-rotating spindles and beveled measurement anvils. Results are then manually recorded on dedicated forms. To improve the efficiency and the metrological reliability of the process, a novel thickness measurement system for nuclear fuel plates was developed. This work presents a comprehensive metrological study of the newly designed measurement system, achieved through the construction of a new apparatus with automated mechanisms for synchronized movement, data capture, transcription, and processing. The study results demonstrate the metrological adequacy of the developed system and underscore the importance of the design and structural quality of the measurement equipment. Consequently, the metrological reliability of the results in the dimensional control of nuclear fuel plates is confirmed.
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.
Emprego de rotas eletroquímicas na separação seletiva e de alto rendimento de iodo-131 para aplicação como radiofármaco
2022 - MARINHO, T.C.; CARVALHO, E.F.U.; FERNANDES, V.C.; SANTIAGO, E.I.
O iodo-131 é um radiofármaco emissor de partícula β- , utilizado no tratamento do câncer de tireóide. Os processos de produção do iodo-131 via fissão de urânio-235 ou irradiação de alvos de telúrio, resultam em soluções compostas por diferentes metais, como molibdênio (Mo), telúrio (Te) e rutênio (Ru). O objetivo deste trabalho foi empregar rotas eletroquímicas baseadas na mudança de temperatura e aplicação de potencial para separação de iodo. Inicialmente Mo, Te e Ru foram analisados quanto à sua interferência no processo de separação e o iodo quanto ao potencial em que a reação se processa com maior velocidade. Em seguida, o iodo foi separado, capturado e testado qualitativamente. Os testes indicaram boa captura em 25° C e 40 °C e pouca captura em 60 °C.