BRIGITTE ROXANA SOREANU PECEQUILO

Resumo

Bachelor in Physics, University of São Paulo (1967), Master in Nuclear Technology, University of São Paulo (1971) and PhD in Nuclear Technology, University of São Paulo (1977). Was researcher at the Institute of Energy and Nuclear Research (IPEN) from 1969 to 2014. Currently is a collaborator of IPEN with the project "Gamma Spectrometry and trace detectors as tools for evaluation of natural and artificial radioactivity in several samples" and superviser at the Graduate Program of IPEN. Has experience in nuclear engineering, with emphasis on Radioisotopes Applications, acting on the following topics: nuclear instrumentation, dose assessment, environmental monitoring, natural radioactivity, alpha and gamma spectrometry, gross alpha and beta radioactivity measurements and nuclear trace detectors . As IAEA expert in the determination of radioactivity concentrations with alpha and gross beta counting systems with low background proportional detector had been in Asuncion, Paraguay (2004) and in Cuenca, Ecuador (2007). Since 1978 is professor in charge of the graduate course of IPEN, Advanced Topics in Nuclear Measurements. (Text obtained from the Currículo Lattes on October 6th 2021)


Possui graduação em Bacharel Em Física pela Universidade de São Paulo (1967), mestrado em Tecnologia Nuclear pela Universidade de São Paulo (1971) e doutorado em Tecnologia Nuclear pela Universidade de São Paulo (1977). Foi pesquisadora do Instituto de Pesquisas Energéticas e Nucleares (IPEN) de 1969 a 2014. Atualmente é colaboradora do IPEN com o projeto "Espectrometria gama e detectores de traços como ferramentas para avaliação de radioatividade natural e artificial em amostras diversas" e orientadora no Programa de Pós-Graduação do IPEN. Tem experiência na área de Engenharia Nuclear, com ênfase em Aplicações de Radioisótopos, atuando principalmente nos seguintes temas: instrumentação nuclear, avaliação de dose, monitoracao ambiental, radioatividade natural, espectrometria alfa e gama, medidas de radioatividade alfa e beta total e detectores de traços. Como expert da AIEA na operacionalização de sistemas de contagem alfa e beta total com detector proporcional de baixa radiação de fundo para a determinação da concentração de radioatividade em água potável, esteve em Assunção, Paraguai (2004) e em Cuenca, Equador (2007). Desde 1978 é professora-responsável do curso de pós-graduação do IPEN, Tópicos Avançados de Medidas Nucleares. (Texto extraído do Currículo Lattes em 06 out. 2021)

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Agora exibindo 1 - 10 de 28
  • Resumo IPEN-doc 30137
    Multielemental characterization of the pollen produced by Scaptotrigona aff postica bee from Brazil using EDXRF technique
    2023 - SILVA, DALTON G.N. da; ZAMBONI, CIBELE B.; PECEQUILO, BRIGITTE R.S.; ESPOSITO, SELENE E.; PIMENTA, DANIEL C.; SIMONS, SIMONE M.
    The objective of this investigation was to perform a multielemental characterization of the pollen produced by Scaptotrigona aff Postiça Bee (popularly known as “tubi”). In recent years, the demand for natural and healthy products has grown significantly and products from Meliponiculture (creation of stingless bees) have started to be consumed on a larger scale in Brazil. Specifically, pollen has gained prominence in the nutritional field for being a protein source and rich in carbohydrates, lipids, mineral trace elements, fibers, hormones and vitamins, but scientific research is still scarce, especially regarding studies of its specific composition. The aim of this investigation was to evaluate the content of inorganic elements (multielemental analysis) in pollen from “tubi” bees. Pollen samples were collected during a one year, in a meliponary of Barra do Corda city, in the state of Maranhão. The EDXRF analyzes were carried out using an X-Ray Fluorescence spectrometer (X-123SDD, Amptek), constituted by a Silicon detector coupled a mini X-ray tube (Ag). These data are the first estimates of mineral trace elements in this natural product and provide benefits to beekeepers regarding their characteristic specifications. In addition contributes with relevant data in the nutritional field.
  • Resumo IPEN-doc 29294
    Traceability of the propolis produced by Scaptotrigona Aff Postica bee from Brazil using NAA technique
    2022 - ZAMBONI, C.B.; GIOVANNI, D.N.S.; PECEQUILO, B.R.S.; ESPOSITO, S.E.; PIMENTA, D.C.; SIMONS, S.M.
    In the Northeast, meliponiculture presents itself as one of the zootechnical activities that has grown the most in recent years, due to its low implementation and maintenance cost, as well as a quick financial return. Meliponiculture is the creation of stingless bees (Meliponines) for the production and commercialization of beehives, honey, propolis, pollen and resins, in addition to these bees being the main agents of pollination and conservation of local biodiversity. The propolis produced by the Scaptotrigona Aff Postica bee (popularly known as the tubi bee) have several medical applications (bactericidal, fungicidal and virucidal), in addition to its use in the nutritional field. This species is found in the mainly in the Barra do Corda County (Maranhão) and it is the major source of income in the northeast region. Nowadays, food authentication has been a concern of producers and consumers around the world. For this reason, there is a growing need for reliable analytical techniques to provide an answer about food authenticity. With the goal for determining chemical descriptors for geographic origin (standardization), nuclear techniques are useful analytical tools with a highlight for Neutron Activation Analysis (NAA). The NAA measurement was performed in the nuclear reactor (IEA-R1, 3-4 MW, at IPEN). Propolis samples were collected monthly during a one year, directly from beehives of Scaptotrigona Aff Postica in a meliponary of Barra do Corda city (5° 30' 21'' S and 45° 14' 6'' W). The results were compared with two other species from south region. The database will aid in fraud detection of the propolis from the northeast region in Brazil.
  • Resumo IPEN-doc 27040
    Activity concentrations of natural and artificial radionuclides in feline dry food
    2015 - CAVALCANTE, F.; PECEQUILO, B.R.S.; LEONARDO, L.
    Natural radiation exposure is an inherent condition to all living species, once radionuclides from the 238U and 232Th chain can nearly be found in all places. Information on radionuclides concentration and exposure levels, from natural and anthropogenic sources are absolutely necessary to investigate the possible effects that ionizing radiation can induce. These can be very different depending on the organism considered and the exposure pathway. In recent decades, the exposure of non-human species to ionizing radiation has been specially considered and investigated (ICRP, 2014) by a vast number of scientists and organizations, once they differ widely from the exposure of human beings. Brazil holds the second largest cat and dog population in the world, consuming over 2 million tons of feed every year. The country also stands out for its production of pet food that produced 2.4 million of tons of feed in 2014, representing the world’s second largest industry. A novel study regarding the radionuclide content in different dog and cat food is being developed since 2013 and preliminary results have been presented by Cavalcante, F. and Pecequilo (2014), for selected dry dog food. The present study presents an evaluation of the radionuclide and radioactivity content of different brands of dry cat food, commonly found in local markets in the city of Sao Paulo, Brazil. Thirteen different samples were crushed into powder and kiln dried before tightly sealed in 100 mL HDPE flasks, with a plan screw cap and bubble spigot. These samples, after resting for 30 days to ensure secular equilibrium, were placed in an extended range coaxial germanium detector (Canberra XtRa GX4020 detector) for 150 ks and the acquired spectra were analyzed with the InterWinner 6.0 software (InterWinner, 2004). The natural radionuclides considered were 238U, 232Th and 40K, the anthropogenic radionuclides investigated were 60Co, 131I, 137Cs and 134Cs. The results for the considered artificial radionuclides have shown activity concentration values below the detector’s MDA (Minimum Detectable Activity), as in Table 1. The concentrations of natural radionuclides ranged from 1.12 ± 0.29 Bq/kg to 3.77 ± 0.36 Bq/kg for 226Ra; from 1.48 ± 0.40 Bq/kg to 6.27 ± 0.78 Bq/kg for 232Th and from 216.8 ± 11.2 Bq/kg to 361.7 ± 16.8 Bq/kg for 40K, as shown in Figure 1. The results suggest that the samples evaluated have no contamination of artificial radionuclides and the natural radionuclides concentration will not contribute to significant absorbed dose by their ingestion. Therefore, the authors conclude that these studied brands carry no radiological risk for the animals ingesting them.
  • Resumo IPEN-doc 25938
    Self-attenuation factors in gamma-ray spectrometry of samples containing radionuclides of natural origin
    2018 - PECEQUILO, B.R.S.; CAVALCANTE, F.; BARROS, L.F.; FERREIRA, A.O.; FONSECA, L.M.; MATEUS, C.
    High resolution gamma-ray spectrometry is currently the most widely used analytical technique for qualitative and quantitative determination of radionuclides. Quantification of elements relies on the correct analysis of the spectra, depending strongly on the efficiency calibration of the measurement apparatus, most often performed with aqueous standard multi-radionuclide solutions. For efficiency calibration curves obtained by this method and for samples containing radionuclides of natural origin such as sand, soil, rocks and wall paint with apparent typical densities higher than that of water, self-attenuation correction factors were experimentally determined for hundreds of different samples using the Cutshall transmission technique. The results show that, to obtain more reliable analyses, correction factors for the self-attenuation behaviour, especially in the lower part of the energy spectrum, should be used. Since attenuation depends not only on the density of the sample but also on its chemical composition, correction factors have to be determined for each sample.
  • Resumo IPEN-doc 25937
    Concentrations of 226Ra, 232Th and 40K in Brazilian wall paint
    2018 - FONSECA, L.M.; PECEQUILO, B.R.S.
    Geological materials used as building materials are a source of radiation exposure due to the presence of radionuclides of natural origin. Wall paint is one of the building materials to be considered for radiological evaluation as it generally contains titanium dioxide pigment obtained from minerals such as ilmenite and rutile which contain 238U and 232Th series radionuclides and 40K. In this work, radionuclide concentrations were determined in 50 commercial Brazilian white latex wall paints using high resolution gamma-ray spectrometry. The following activity concentrations were measured: 1.41–38.7 Bq/kg (226Ra), 0.9–101.2 Bq/kg (232Th) and 5.9–256 Bq/kg (40K). These results demonstrate that the wall paints studied in this work are safe for use.
  • Resumo IPEN-doc 24586
    An overview of the gaseous radioactive effluents control and radioactivity assessment in the atmospheric air at IPEN’S campus
    2017 - RODRIGUES, C.E.C.; NOGUEIRA, P.R.; DAMATTO, S.R.; MADUAR, M.F.; ALENCAR, M.M.; PECEQUILO, B.R.S.
    The routine operation of a nuclear or radioactive installation generally involves the release of radioactive liquid and/or gaseous effluents. At the Nuclear and Energy Research Institute – IPEN there are several nuclear and radioactive facilities, developing activities in the field of nuclear energy. IPEN’s Radioprotection Management has established a radioactive effluent sampling program to determine the amount of radioactive material (source term) released into the environment and to detect immediately any unplanned release above the pre-established operating limits. The IPEN Environmental Radiological Monitoring Program – ERMP evaluates the levels of radioactivity to which individuals of the public are exposed through the analysis of atmospheric samples; the main objective of an ERMP is the confirmatory radiological control, which estimates whether the assumptions made in the calculation of the dose, from the source term, are correct. The objective of the present work is to present the gaseous radioactive effluents control and the radioactivity assessment in the atmospheric air at IPEN’s campus, since there were implanted in 1988 at the Laboratory of Environmental Radiometry of IPEN. In both, gaseous radioactive effluents control and radioactivity assessment in the atmospheric, cellulose and charcoal cartridge filters are analyzed by gamma spectrometry – HPGe weekly, from the IPEN’s radioactive facilities, Accelerators and Cyclotron Center, IEA-R1 Research Reactor Center, Radiopharmacy Center - Building I and II and each 15 days collected from three air samplers located near the nuclear and radiation facilities of IPEN, respectively. The radionuclides determined in the majority of the samples throughout the sampling period were 131I, 18F and 67Ga.
  • Resumo IPEN-doc 22978
    226Ra, 232Th and 40K concentrations in Brazilian wall paints
    2016 - FONSECA, LEANDRO M. da; PECEQUILO, BRIGITTE R.S.
    Geological materials used as building materials act as a source of radiation due to primordial radionuclides as the single radioactive isotope of potassium 40K and radioisotopes from the uranium 238U and 232Th series. Wall paints are one of the building materials to be considered for dose rates evaluation, as, beside other components, contain pigments, mainly titanium dioxide. As titanium dioxide is obtained from minerals as rutile and ilmenite, with thorium and uranium traces, the activity concentration of natural radionuclides in wall paints should be determined, for further annual effective dose assessment in a construction. In this work, activity concentrations of 226Ra, 232Th and 40K were determined by high-resolution gamma-ray spectrometry in 50 commercial brazilian white latex wall paints samples. The activity concentration values for 226Ra ranged from 1.41 Bq.kg-1 to 38.7 Bq.kg-1, for 232Th from 0.9 Bq.kg-1 to 101.2 Bq.kg-1 and for 40K from 5.9 Bq.kg-1 to 256 Bq.kg-1. The results show that the activity concentrations of the wall paints studied in this work are in a safe range for use for all the 50 samples.
  • Resumo IPEN-doc 22816
    Self-attenuation factors in gamma-ray spectrometry of NORM samples
    2016 - PECEQUILO, BRIGITTE R.S.; CAVALCANTE, FERNANDA; BARROS, LIVIA F.; FERREIRA, ADEMAR O.; FONSECA, LEANDRO M.; MATEUS, CRISLENE
  • Resumo IPEN-doc 22313
    Factors affecting the sup(7)Be concentration in surface air over a long period of monitoring in São Paulo, Brazil
    2014 - DAMATTO, SANDRA; MADUAR, MARCELO; PECEQUILO, BRIGITTE; NOGUEIRA, PAULO; NISTI, MARCELO