MARCELO FRANCIS MADUAR

MARCELO FRANCIS MADUAR

(Fonte: Lattes)

Resumo

Doctorate (2010) and Master (2000) degrees in Nuclear Technology at São Paulo University, Physics Bachelorate at São Paulo University (1996) and Technologist in Data Processing at Universidade Estadual Paulista Júlio de Mesquita Filho (1989). Experience in Experimental Physics, focusing on Experimental Methods and Instrumentation for Elementary Particles and Nuclear Physics. (Text obtained from the Currículo Lattes on November 16th 2021)

Doutorado (2010) e Mestrado (2000) em Tecnologia Nuclear pela Universidade de São Paulo, Bacharelado em Física pela Universidade de São Paulo (1996) e graduação em Tecnologia Em Processamento de Dados pela Universidade Estadual Paulista Júlio de Mesquita Filho (1989). Tecnologista senior do Instituto de Pesquisas Energéticas e Nucleres (IPEN), órgão da Comissão Nacional de Energia Nuclear (CNEN). Gerente adjunto (desde julho/2018) do Serviço de Gestão de Radiometria Ambiental (SEGRA) do IPEN. Tem experiência na área de Física, com ênfase em Métodos Experimentais e Instrumentação para Detectores de Radiação, atuando principalmente nos seguintes temas: espectrometria gama, radioatividade ambiental e aplicação de métodos computacionais na avaliação de espectros gama, em modelos de dispersão ambiental e em dose externa decorrente de radiação gama. Orientador de Mestrado do Programa de Pós-Graduação em Tecnologia Nuclear do IPEN - área de Aplicações (TNA) a partir de maio de 2019 e docente das disciplinas TNA5754, Radioatividade no meio ambiente e avaliação de impacto radiológico ambiental, e TNA5733, Tópicos Avançados de Medidas Nucleares. (Texto extraído do Currículo Lattes em 16 nov. 2021)

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Radiation dose assessment from NORM residue used in the circular economy
2024 - NISTI, MARCELO; SAUEIA, CATIA; DAMATTO, SANDRA; MADUAR, MARCELO
Biota and human beings are exposed to naturally occurring radionuclides present in several natural resources [1]. Phosphogypsum (PG) is classified as a Naturally Occurring Radioactive Material (NORM) residue of the phosphate fertilizer industry. PG residue presents in its composition radionuclides of the natural U and Th decay series and stored in stacks by the phosphate industries, which can represent risks to environment and human from the radiological protection point of view, such as: atmospheric contamination, pollution of groundwater, trace elements and radionuclides, radon emanation, inhalation of dust and direct exposure to gamma radiation. Some possible applications of this residue are soil conditioners, resulting in an increase of agriculture productivity, or building materials [2]. The Brazilian regulatory body ruled that PG would only be permitted for use in agriculture if 226Ra and 228Ra activity concentrations do not exceed 1 Bq g-1, for each radionuclide [3]. On the other hand, the safe reuse of PG residue avoids depletion of non-renewable resources, decreases the stacks and consequent reduces the possible environmental impact. Also adds value to PG, considering the principles of sustainable development and the principle of the circular economy. This study's aims were to evaluate the estimated radiation doses in biotas and humans considering two scenarios: PG stack and application of PG in agriculture, using the ERICA Tool 2.0 [4] and NORMALYSA Tool 2.0 [5]. For the PG stack, estimated radiation doses (external and internal) to the worker and biota around the stack were evaluated. In the agriculture (soil amended with PG residue), the estimated radiation doses to the farmer (external and internal), consumers of agricultural products (internal) and biota (external and internal) were evaluated. In this paper, one application per year of PG residue in the soil and the maximum value of the Brazilian regulatory were considered.
One year of Be-7 measurement in rainfall collected in different points in the city of São Paulo, Brazil
2024 - DOMINGOS, R.M.; LEONARDO, L.; DAMATTO, S.R.; MIRANDA JUNIOR, P.; ISIKI, V.L.; NISTI, M.B.; ALENCAR, M.M.; TEIXEIRA, L.F.L.; MADUAR, M.F.; NETO, J.O.A.
Pb-210 activity concentration measured in rainfall in different sampling heights
2024 - ALMEIDA NETO, J.O.; DAMATTO, S.R.; MADUAR, M.F.; LEONARDO, L.; TEIXEIRA, L.F.L.
In situ characterization of NORM waste from the oil industry
2022 - DELLAMANO, J.C.; DAMATTO, S.R.; CARVALHO, R.N.; MENEGHINI, A.A.; MARUMO, J.T.; MADUAR, M.F.; VICENTE, R.
In the oil industry, radioactive wastes are generated in the oil production platforms containing natural radionuclides, such as 226Ra and 228Ra, the NORM waste. This waste is mainly in the form of produced water, sludge and scales which should be characterized for the correct final destination. The Brazilian laws establish that the NORM wastes from the oil production must comply with Law 10308 of November 20, 2001, which determine in its article 7, "The disposal of radioactive waste of any kind in the oceanic islands, the continental shelf and the Brazilian territorial waters is prohibited." Therefore, the NORM waste from offshore oil extraction rigs should be transported to onshore facilities. There are two options for the destination of this material: industrial landfill, in the case of activity concentrations are below clearance limits established by Brazilian Nuclear Commission, CNEN; or on the contrary, to intermediate storage facilities, until final disposal is decided. Currently, the oil production companies take samples from the waste and send them to radiometric laboratories in order to evaluate their activity concentration by gamma spectrometry. The complete process takes more than six months to be concluded. Nuclear and Energy Research Institute, IPEN, is making efforts to solve the management problems of NORM waste from oil extraction, including conduct research aiming at characterizing the waste. The objective of the paper is to present the results of in situ characterization of drums containing oil sludge using portable gamma spectrometers.
In situ characterization of NORM waste from the oil industry
2020 - DELLAMANO, JOSE C.; DAMATTO, SANDRA R.; MADUAR, MARCELO F.; MARUMO, JULIO T.; CARVALHO, RICARDO N.; VICENTE, ROBERTO; MENEGHINI, ARTHUR A.
Estimated absorbed dose rate in the non-human biota in different environmental scenarios
2022 - NISTI, M.B.; MADUAR, M.F.; CAVALCANTE, F.; SAUEIA, C.H.R.
Study of 7Be activity concentration in rainfall as a function of sampling height
2022 - ALMEIDA NETO, J.O.; DAMATTO, S.R.; MADUAR, M.F.; LEONARDO, L.; TEIXEIRA, L.F.; DOMINGOS, R.M.
Natural radioactivity in oilseeds commercialized in the city of São Paulo, Brazil
2022 - LEONARDO, L.; DAMATTO, S.R.; MADUAR, M.F.
Counting efficiency in gamma-ray spectrometry with different sample volumes for the same geometry
2022 - NISTI, M.B.; MADUAR, M.F.; DAMATTO, S.R.; ALENCAR, M.M.
The aim of this study is to determine an easy and fast method to calculate efficiencies in different volumes, in the same counting geometry, for gamma-ray spectrometry technique. Reference Material Soil IAEA 326 was packed in a 100 mL capacity polyethylene bottle with different masses and volumes, and sealed for about four weeks, prior measurement, in order to ensure that radioactive equilibrium had been reached between 226Ra and its progeny. After this time, they were measured by gamma-ray spectrometry with a hyper-pure germanium detector. The masses of the reference material used were 25, 60, 80, 95 and 128g. The energies of gamma-rays used in this paper are recommended due to the considerations: gamma intensity value, peak quality, spectral region without interference and the gamma- ray energies of the 238U and 232Th series very important for determining the natural radioactivity. The efficiency values obtained compared to the adjusted efficiency values were similar and presented a good correlation coefficient. The performance was acceptable for all different masses studied, indicating results consistent for the method. The proposed method could be useful as a tool for laboratories, dealing with of samples on a routine basis, by reducing the cost on the purchase of another counting geometry and optimizing the use of the detection system, thus improving their performance.
Monitoração radiológica dos efluentes gasosos do reator IEA-R1 do IPEN
2022 - GABRIEL, LUIZ H.; RODRIGUES, CARLOS E.C.; NOGUEIRA, PAULO R.; DAMATTO, SANDRA R.; ISIKI, VERA L.K.; TEIXEIRA, LUIZ F.L.; MADUAR, MARCELO F.; ALENCAR, MARCOS M.
A operação normal de uma instalação nuclear ou radiativa envolve a liberação de efluentes radioativos líquidos e/ou gasosos. No Instituto de Pesquisas Energéticas e Nucleares (IPEN) existem diversas instalações nucleares e radiativas, desenvolvendo atividades no campo da física nuclear, radioquímica, engenharia nuclear, produção de radioisótopos e radio fármacos, aplicação de técnicas nucleares na indústria entre outras. A Gerência de Radioproteção do IPEN estabeleceu um programa de amostragem dos efluentes radioativos para determinar a quantidade de material radioativo (termo fonte) liberada para o meio ambiente e detectar imediatamente, qualquer liberação não planejada acima dos limites operacionais pré-estabelecidos. O controle radioativo dos efluentes gasosos e do ar atmosférico ambiental do Instituto foi implementado em 1988 e é realizado pelo Laboratório de Radiometria Ambiental – Centro de Metrologia das Radiações. No controle dos efluentes gasosos são analisados semanalmente, por espectrometria gama de alta resolução com detector de germânio hiperpuro, filtros de celulose e de carvão das instalações radioativas do IPEN, como o Centro do Reator de Pesquisas IEA-R1 e também o Centro de Aceleradores e Cíclotron e a Diretoria de Radiofarmácia – Prédio I e II. Desde a operação do controle dos efluentes gasosos há trinta anos, mais de 3000 filtros foram analisados e os radionuclídeos determinados na maioria das amostras durante esse período de amostragem no Centro do Reator de Pesquisas IEA-R1 foram 131I e 123I. Os resultados obtidos das análises dos filtros do controle dos efluentes gasosos são publicados em relatório de avaliação periódica e disponibilizados internamente via intranet. Todos os resultados obtidos, de 1988 a 2018, confirmam que a liberação de efluentes gasosos radioativos da operação normal das instalações nucleares e radioativas do IPEN está sendo adequadamente controlada e que o impacto radiológico causado por essa liberação é insignificante quando comparado aos limites recomendados pela regulamentação atual da CNEN de 2005.