MARYCEL ELENA BARBOZA COTRIM

MARYCEL ELENA BARBOZA COTRIM

(Fonte: Lattes)

ORCID

ScopusID

ResearcherID

Resumo

Bachelor's at Química from Faculdades Osvaldo Cruz (1985), master's at Tecnologia Nuclear from Instituto de Pesquisas Energeticas E Nucleares (1991) and doctorate at Tecnologia Nuclear from Instituto de Pesquisas Energeticas E Nucleares (2006). Has experience in Chemistry, focusing on Separation, acting on the following subjects: avaliação ambiental, metais, química ambiental, qualidade da água and química analítica. (Text obtained from the Currículo Lattes on November 17th 2021)

Mestrado em Tecnologia Nuclear pelo Instituto de Pesquisas Energéticas E Nucleares (1991) e Doutorado em Tecnologia Nuclear pelo Instituto de Pesquisas Energéticas E Nucleares (2006). Atualmente é pesquisador da Comissão Nacional de Energia Nuclear. Experiência em química analítica, atuando principalmente nos seguintes temas: avaliação ambiental, metais, química ambiental, qualidade da água e química analítica, caracterização de compostos de urânio e química analítica instrumental. (Texto extraído do Currículo Lattes em 17 nov. 2021)

Página do item completo

Resultados de Busca

Agora exibindo 1 - 10 de 103

Aspects of higly microplastic contamination in the Atlantic Forest estuary
2023 - PARRA, DUCLERC F.; GIMILIANI, GIOVANA; SANTOS, JACINETE L. dos; COTRIM, MARYCEL E.B.
The Atlantic Forest is one of the richest regions in terms of biodiversity in the world. Originally the biome covered about 15% of the national territory. Currently, only about 12.4% (SOS MATA ATLÂNTICA, 2021) of well-preserved forest remnants remain in the country [1]. Regarding mangrove areas, in the state of São Paulo there are about 223 km², according to the Atlas of mangroves in Brazil, with about 120.5 km² of this total in Baixada Santista. Analyzes of sediments collected at Santos estuarine mangroves, in various points show a high concentration of microplastics generated from industrial processes or even anthropogenic activity. These solid particles based on (< 5 mm) are today one of the main environmental problems. The microplastics present in the sediment samples were quantified after drying and sieving amount limited of sediment. FTIR and micro-Raman spectroscopy identified filaments and fragments of microplastics (MPs) as commom polymer spectra. Also additives and herbicides were present in some MPs. All polymeric types identified (<5mm) have wide applications and demands by packaging, civil construction, automotive, electrical and electronics, and textile sectors.
Use of the ion exchange technique for purification of lithium carbonate for nuclear industry
2021 - ANDRADE, MARIANA N.; OLIVEIRA, GLAUCIA C.; CONTRIM, MARYCEL E.B.; SENEDA, JOSE A.; BUSTILLOS, OSCAR V.
Ion exchange resins applied in the removal of uranium from contaminated effluents
2021 - PIRANI, DEBORA A.; FAUSTINO, MAINARA G.; FURUSAWA, HELIO A.; PEDREIRA FILHO, WALTER dos R.; CONTRIM, MARYCEL E.B.
Chitosan coated magnetite nanoparticles applied in effluent treatment for uranium removal
2021 - PIRANI, DEBORA A.; FAUSTINO, MAINARA G.; PEDREIRA FILHO, WALTER dos R.; FURUSAWA, HELIO A.; CONTRIM, MARYCEL E.B.
Fatores de emissão atmosférica e análise de significância aplicada na gestão da qualidade do ar no campus do IPEN/CNEN-SP
2016 - SANTOS, CAMILA F.R.T.T.; SILVA, TATIANE B. de S.C. da; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F.
Devido ao compromisso com a melhoria do meio ambiente, aliado às crescentes exigências dos órgãos ambientais, e a necessidade de identificar a contribuição de cada atividade/processo desenvolvido em institutos de pesquisas, quanto ao impacto destes à qualidade do ar, este trabalho tem a finalidade de desenvolver um modelo de inventário e aplicar uma metodologia de cálculo, que permita estimar a emissão de poluentes atmosféricos, decorrentes das atividades dos centros de pesquisa e desenvolvimento do Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP). O estudo foi motivado pela ausência de metodologias de cálculo de emissões atmosféricas específicas para fontes fixas como capelas de exaustão. Para a elaboração dos cálculos foram adotados os fatores de emissão e a equação descrita na AP-42 da EPAEnvironmental Protetion Agency. Foram utilizadas como abordagens de cálculo de emissões: a) Mensuração direta (por meio do inventário de emissões atmosféricas); e b) Estimativa de emissões (utilizando estimativa da taxa de emissão calculada a partir do fator de emissão apropriado). Como produto final obteve-se um inventário de emissões atmosféricas de fontes fixas da instituição e estimou-se a emissão atmosférica do Centro de Química e Meio Ambiente (CQMA) a fim de estabelecer de forma efetiva o Programa de Monitoramento e Controle de Emissões Atmosféricas (PMEA – IPEN), servindo de base para outras instituições de Pesquisa, Desenvolvimento & Inovação.
Análise química de liga de grau nuclear aplicada como material de controle em reatores nucleares
2019 - PEREIRA, DEBORA A.; FERREIRA, DOUGLAS A.; FATTE, MARIO; SOUZA, NATALIA DE O.; GIOVEDI, CLAUDIA; COTRIM, MARYCEL E.B.; PIRES, MARIA A.
A liga de prata-indio-cádmio (Ag/In/Cd) é utilizada como material absorvedor em elementos de controle de reatores nucleares devido à alta seção de choque para absorção de nêutrons de seus componentes. Em Reatores Refrigerados a Água Pressurizada (PWR - Pressurized Water Reactor), a liga Ag/In/Cd é utilizada na forma de barra contendo 80% de prata, 15% de índio e 5% de cádmio em massa com tolerâncias, máxima e mínima, bastante rigorosas em sua composição. A liga na forma de barra é encapsulada em tubos metálicos, os quais compõem o conjunto do elemento de controle no reator nuclear. Para ser aplicada com este propósito, a barra de liga Ag/In/Cd deve apresentar uma composição homogênea ao longo de toda a sua extensão, a fim de assegurar seu comportamento adequado dentro do reator. O objetivo deste projeto é desenvolver e qualificar a metodologia de análise química aplicada à caracterização da liga Ag/In/Cd para ser usada em barras de controle em reatores do tipo PWR. A metodologia padronizada para determinar o teor de prata, índio e cádmio na liga de grau nuclear é a titulação potenciométrica para prata e a titulação de complexação para o índio e o cádmio. A precisão dos resultados obtidos depende da prévia calibração dos materiais volumétricos e equipamentos utilizados, bem como da calibração dos reagentes titulantes a serem utilizados na titulação. Além disso, a qualificação desse processo para fins nucleares requer a elaboração de todos os documentos relacionados a cada uma das etapas do processo, incluindo práticas operacionais e registros da qualidade. O desenvolvimento e a qualificação da metodologia representam passos fundamentais no sentido de tornar o Brasil autossuficiente na produção desse material aplicado à área nuclear.
Uranium removal from contaminated water by ion exchange resins
2019 - PIRANI, DEBORA A.; COTRIM, MARYCEL E.B.; OLIVEIRA, GLAUCIA A.C. de; ANDRADE, MARIANA N. de; FURUSAWA, HELIO A.
In the nuclear fuel cycle, uranium containing liquid wastes can be produced in large quantities. There are several possible operations to separate this element from an aqueous solution. The classic examples are separation by solvent extraction and by precipitation when uranium is present in high concentrated solutions. In those cases where the element is present in concentrations as low as 100-200 μg mL-1, ion exchange technique can be very helpful to bring the uranium concentration to less than 10-20 ug mL-1. The synthetic resins used in ion exchange processes effectively remove metals from contaminated liquid wastes. This work intends to remove uranium from aqueous solutions by ion exchange technique. A column (10 cm in height and 1 cm in diameter) was used with 30 ml of dry Dowex 1-X8 strong anionic resin to fix and remove uranium from the solution. The solution with 155 mg.L-1 of uranium was percolated through the column with a flow of 4.0 mL.min-1. Resin was conditioned at pH = 7. The determination of the uranium contents was performed by Optical Emission Spectrometry with Argon Plasma Source (ICP-OES). The main operational parameters, such as pH, flow and column height, were evaluated to determine the best operating condition of the system. The results indicated approximately 99.9% removal of uranium from the application of the ion exchange technique. The percentage of removal allows the effluent to be properly disposed of in a sewage collection system in accordance with the regulations in force in the country.
Estimated pollutant load from nuclear and energy research institute (IPEN/CNEN-SP, Brazil)
2019 - SILVA, TATIANE B. de S.C. da; OLIVEIRA, CINTIA C. de; MARQUES, JOYCE R.; FAUSTINO, MAINARA G.; STELLATO, THAMIRIS B.; MONTEIRO, LUCILENA R.; PIRES, MARIA A.F.; CONTRIM, MARYCEL E.B.
Quantifying the pollutant load in a receiving water body is one of the needed steps to keep its original standards, irrespective of its releases source. Monitoring, and thus, controlling the amount of pollutants to be destined to the water body means ensuring water quality, keeping it free of excessive pollution and harm to human health and the environment. Hence, this paper aims to estimate the pollutant load of sanitary wastewater released by the Nuclear and Energy Research Institute (IPEN / CNEN-SP) during 2015 and 2016. The assay of Cd, Pb, Cu, Cr, Zn, Ba, Ni, Mn, Fe, B and Sn were performed by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) and As, Hg and Se by Graphite Furnace Atomic Absorption Spectrometry (GF-AAS). The metals and total fixed solids pollutant load estimative carried out, employed wastewater flow measurement, using bromide (Br- ) as tracer and the annual water consumption at IPEN. This evaluation is performed annually by IPEN since 2006 as part of the Environmental Monitoring Program (PMA-Q), in order to comply with the current environmental legislation and the Term of Adjustment of Conduct requirements, agreed with the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA).
Applying multi-incremental sampling methodology to soils for radiological and environmental risks evaluation
2019 - MANTOVANI, JULIANA; SCAPIN, MARCOS A.; MACACCINI, JOSÉ. F.; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F.
Multi-increment soil sampling is a methodology that allows evaluating environmental liability inside decision unit, providing a representative aliquot for laboratory analysis with associated uncertainties lower than conventional sampling. The literature has reported much works about environmental liabilities evaluation in soil using multi-increment sampling however, for nuclear facilities soils are practically nonexistent. Therefore, aim of this study was to determinate radionuclides concentration (by Gamma spectroscopy), major and minor constituents (by X-ray fluorescence spectrometry) and metals (by Inductively Coupled Plasma-Atomic Emission Spectrometry) in soils of nuclear material storage facilities in Nuclear and Energy Research Institute (IPEN/CNEN-SP) using multi-increment sampling. The natural radionuclides (210Pb, 226Ra, 228Ra, 238U), major and minor constituents (MgO, Al2O3, SiO2, P2O5, K2O, CaO, TiO2, and others) and metals (Cr, Fe, Co, Ni, Zn, As, Pb, and other) were determined in 120 soil samples, in-depth between 0 and 150 mm at 30 quadrants. The results showed specific activity of 57 ± 16 Bq kg-1 (210Pb), 51 ± 22 Bq kg-1 (226Ra), 81 ± 12 Bq kg-1 (228Ra) and 48 ± 14 Bq kg-1 (238U), corresponding uncontaminated soil, according reference values. With regarding metals concentration, results also were lower than values reference. The statistical tests showed that methodology is efficient for environmental impact studies and monitoring programs and adequate to attend established conditions in IPEN-CNEN / SP environmental licensing.
Direct determination of aluminum in low-enriched UALx targets ( UAlx-Al) by inductively coupled plasma optical emission spectrometry
2019 - GUILHEN, SABINE N.; SOUZA, ALEXANDRE L.; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F.
The production of molybdenum-99 (99Mo) using low-enriched uranium targets (< 20% 235U) dispersed in aluminum (UAlx) is a very promising strategy towards the independence in 99Mo local production. A thorough control must be performed to ensure that these targets meet the regulatory requirements to achieve the expected efficiency in the reactor. The determination of the targets’ composition is of high interest, because the distribution of Al in different phases may have an impact on the U concentration. Among the techniques used for this purpose, inductively coupled plasma optical emission spectrometry (ICP OES) stands out because of its high sensitivity and precision, allowing for simultaneous determination of several elements in a variety of samples and matrices. However, because U exhibits a complex emission spectrum, spectral interferences are prone to affect the analysis of Al, calling for time consuming preparation steps to remove the U from the matrix. This study proposes a method of direct determination of Al in UAlx targets through the selection of specific emission lines enabled by the evaluation of the associated interferences on the recovery values.