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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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.
16 anos de resultados de determinação de radionuclídeos emissores gama na água da piscina do reator IEA-R1
2022 - MADUAR, MARCELO F.; ALENCAR, MARCOS M. de; TEIXEIRA, LUIZ F.L.; NISTI, MARCELO B.
A avaliação dos parâmetros técnicos na operação do Reator de Pesquisas IEA-R1, em particular as características físico-químicos da água da piscina do IEA-R1, é parte integrante das atividades coordenadas pelo CRPq (Centro do Reator de Pesquisas) do IPEN. O Serviço de Gestão de Radiometria Ambiental realiza desde meados de 2003 a análise rotineira por espectrometria gama em amostras da água da piscina do IEA-R1. Os radionuclídeos usualmente detectados são: Ag-110m, Co-58, Co-60, Cr-51, I-131, Mn-54, Na-24, Np-239, Te- 132, W-187 e Zn-65. Alguns nuclídeos são detectados raramente, como Cs-137, Ba-140/ La-140 e Ru-103. O radionuclídeo que apresenta regularmente a maior atividade é Na-24, com concentrações na faixa de 100 a 150 kBq/L, corrigida para o horário de desligamento do IEA-R1. Outros apresentam radioatividade da ordem de 102 a 103 Bq/L (Ag-110m, Co-58, Co-60, Cr-51 e W-187) e os restantes, poucos Bq/L. A principal conclusão, ao longo do tempo, é que o tempo de espera após o desligamento e coleta das amostras é o fator fundamental na definição de quais radionuclídeos são e quais não são passíveis de quantificação radiométrica. As medidas realizadas entre cinco e sete dias após o desligamento do reator fornecem um compromisso ótimo na detecção de nuclídeos de meia-vida inferior a um dia e limites de detecção aceitáveis para nuclídeos de meia-vida superior a dez dias.
Gamma spectrometry of iodine-125 produced in IEA-R1 nuclear reactor, using HPGe detector and fixation into epoxy matrix disc
2021 - COSTA, OSVALDO L. da; SOUZA, DAIANE C.B. de; CASTANHO, FABIO G.; FEHER, ANSELMO; MOURA, JOÃO A.; SOUZA, CARLA D.; OLIVEIRA, HENRIQUE B.; MADUAR, MARCELO F.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.
Few places in the world produce iodine-125. In Brazil, the first production was achieved by using the IEA-R1 nuclear reactor located at Nuclear and Energy Research Institute – IPEN. To verify the quality of iodine-125 produced, and the amount of contaminants such as iodine-126, cesium-134 and caesium-137 among others, iodine-125 samples were immobilized into epoxy matrix disc, with the same geometry of a barium-133 reference radioactive source, used to calibrate an HPGe detector. The HPGe detector has a thin carbon composite window, which allows measure the iodine-125 photopeaks, between 27.1 and 35.4 keV. The method employed here was successful in producing and measurement of iodine-125.
Optimization of the gamma-ray spectrometry counting time based on uncertainties of radionuclides concentration in samples
2020 - NISTI, M.B.; MADUAR, M.F.; SAUEIA, C.H.R.; CAVALCANTE, F.; MAZZILLI, B.P.
This paper aims to propose an easy and fast method of optimization of the gamma-ray spectrometry counting time in determining natural radionuclides (210Pb, 212Pb, 214Pb, 212Bi, 214Bi and 228Ac) in order to minimize uncertainties in the concentration. The samples were measured by gamma-ray spectrometry with a hyper-pure germanium detector Canberra, 25% relative efficiency, effective resolution of 1.9 keV on the 1332.5 keV 60Co with associated electronics and coupled to a microcomputer. Multichannel Maestro A65-I model was used for spectrum acquisition and peak net area determination, and WinnerGamma/Interwinner 6.01 software was used for gamma-ray spectra analysis and to calculate the concentrations and associated uncertainties. The counting times used were 86,000 s and 150,000 s.
Gamma spectrometry of iodine-125 produced in IEA-R1 nuclear reator, using HPGe detector and fixation into epoxy matrix disc
2019 - COSTA, OSVALDO L. da; SOUZA, DAIANE C.B. de; CASTANHO, FABIO G.; FEHER, ANSELMO; MOURA, JOÃO A.; SOUZA, CARLA D. de; OLIVEIRA, HENRIQUE B. de; MADUAR, MARCELO F.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.
Few places in the world produce iodine-125. In Brazil, the first production happened in nuclear reactor IEA-R1 located at Nuclear and Energy Research Institute – IPEN. To verify the quality of iodine-125 produced, because contaminants as iodine-126, caesium-134 and caesium-137 among others, may be produced in irradiation process, iodine-125 samples were immobilized into epoxy matrix disc, with the same geometry of a barium-133 reference radioactive source, used to calibrate an HPGe detector. The HPGe detector has a thin carbon composite window, which allows measure the iodine-125 photopeaks, between 27.1 and 35.4 keV.
External and internal annual effective doses for Parana state granites used as internal coating building materials by high resolution gamma-ray spectrometry
2015 - FERREIRA, A.O.; PECEQUILO, B.R.S.; MADUAR, M.F.
sup(7)Be concentration in air surface over a long period of monitoring in the city of São Paulo, Brazil
2015 - DAMATTO, S.R.; MADUAR, M.F.; PECEQUILO, B.R.S.; NOGUEIRA, P.R.; NISTI, M.B.
Gamma-ray emitter radionuclides in soils from an Institute of Technology Campus in São Paulo City
2014 - SANTOS, SANTIAGO S.; MADUAR, MARCELO F.; MIRANDA JUNIOR, PEDRO
Seasonal variation of sup(7)Be concentrations measured at ground level air in São Paulo - Brazil
2011 - DAMATTO, S.R.; MADUAR, M.F.; PECEQUILO, B.R.S.; NISTI, M.B.
External exposure due to phosphogypsum plates used as building material
2008 - VILLAVERDE, F.L.; CAMPOS, M.P.; MADUAR, M.F.; MAZZILLI, B.P.