MARCELO FRANCIS MADUAR

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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Resultados de Busca

Agora exibindo 1 - 7 de 7
  • Artigo IPEN-doc 29126
    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.
  • Artigo IPEN-doc 28199
    Counting time optimization for gamma-ray spectrometry analysis
    2021 - NISTI, M.B.; MADUAR, M.F.; SAUEIA, C.H.R.; CAVALCANTE, F.
  • Artigo IPEN-doc 23539
    A dose calculation model application for indoor exposure to two-layer walls gamma irradiation: the case study of ceramic tiles
    2016 - RIGHI, SERENA; VERITA, SIMONA; ROSSI, PIER L.; MADUAR, MARCELO F.
    A calculation model for determining the indoor dose due to building materials with significant concentration of radioactivity has been applied to the case study of ceramic tiles; the model allows the contribution of bearing walls and wall covering materials to be calculated. The model is implemented in FORTRAN 77 and provides a quantification of the gamma radiation field (in terms of external dose rate in air, nGyh21) inside a room with known dimensions. Application model results have been validated both by comparison with the results obtained by other authors and by experimental measurements. Model sensitivity and performances have been analysed and lastly the case studies focused on ceramic tiles have been proposed.
  • Artigo IPEN-doc 08488
  • Artigo IPEN-doc 06588
  • Artigo IPEN-doc 10242
    Evaluation of indoor gamma radiation dose in dwellings
    2004 - MADUAR, M.F.; HIROMOTO, G.
  • Artigo IPEN-doc 17375
    Assessment of external gamma exposure and radon levels in a dwelling constructed with phosphogypsum plates
    2011 - MADUAR, M.F.; CAMPOS, M.P.; MAZZILLI, B.P.; VILLAVERDE, F.L.