ANSELMO FEHER

(Fonte: Lattes)
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Graduado em Tecnologia Mecânica com ênfase em soldagem pela Faculdade de Tecnologia de São Paulo (1992), possui mestrado em Tecnologia Nuclear pela Universidade de São Paulo (2006) e doutorado em Tecnologia Nuclear pela Universidade de São Paulo (2014). Atualmente é Servidor Público Federal da Comissão Nacional de Energia Nuclear, órgão vinculado ao Ministério da Ciência, Tecnologia e Inovação. Tem experiência nas áreas de Engenharia Mecânica e Aplicações Nucleares, atuando principalmente em desenvolvimento e manutenção de sistemas de alto vácuo, ensaios de detecção de vazamentos utilizando espectrômetros de massa para gás hélio, produção de fontes radioativas seladas, soldagem por arco plasma, soldagem a laser, braquiterapia, sementes de iodo-125 e fontes de irídio-192 para tratamento de câncer. (Texto extraído do Currículo Lattes em 28 mar. 2023)

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2018 - 201912020 - 20212
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Fator de Impacto: 1.500 - 2.999 × Tem arquivos: true ×

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  • Imagem de Miniatura
    Artigo IPEN-doc 27743
    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.
  • Imagem de Miniatura
    Artigo IPEN-doc 27362
    New core configuration for the fabrication of 125I radioactive sources for cancer treatment
    2020 - SOUZA, CARLA D. de; ZEITUNI, CARLOS A.; FEHER, ANSELMO; MOURA, JOÃO A.; COSTA, OSVALDO L. da; ANGELOCCI, LUCAS V.; ROSTELATO, MARIA E.C.M.
    In order to provide prostate brachytherapy treatment for more Brazilian men, IPEN is building a laboratory for the manufacture of radioactive sources. The new methodology for the production of iodine-125 seeds with yield 71.7% ± 5.3%. Points of importance were evaluated/discussed: photo-sensibility, reaction vial type, the substitution for iodine-131, pH, and solution volume. The surface was analyzed by FTIR and EDS. At the end, a Monte Carlo-MCNP6 simulation was performed to evaluate the TG-43 parameters.
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    Artigo IPEN-doc 24717
    Irradiation system for production of gaseous radioisotopes used as tracers in industrial process measurements
    2018 - CARDOZO, N.X.; OMI, N.M.; AMBIEL, J.J.; FEHER, A.; NAPOLITANO, C.M.; SOMESSARI, S.L.; CALVO, W.A.P.
    The use of radioisotopes as radiotracers is considered the most important in diagnosing operation and troubleshooting of industrial process plants in chemical and petrochemical companies. They are used in analytical procedures to obtain qualitative and quantitative data systems, in physical and physicochemical studies transfers. In the production of gaseous radioisotopes used as tracers in industrial process measurements, argon-41 (41Ar) and krypton-79 (79Kr) stand out because each has low reactivity with other chemical elements. 41Ar is a transmitter range with high-energy (1.29 MeV) and a high percentage of this energy transformation (99.1%), resulting in relatively small quantities required in relation to the other, for an efficient detection, even in large thicknesses components. Nowadays, the production of gaseous radioisotopes in nuclear research reactors is performed in small quantities (batches), through quartz ampoules containing natural gas 40Ar or 78Kr. In this sense, the aim of this study is to develop an irradiation system for gaseous radioisotope production in continuous scale, applied in industrial applications of emission tomography and flow measurement. The irradiation system may produce 41Ar with activity of 7.4×1011 Bq (20 Ci) per irradiation cycle, through the Reactor IEA-R1 with 4.5MW and average thermal neutron flux of 4.71×1013 ncm−2s−1 to meet an existing demand in NDT and inspections companies, and even needed by the Radiation Technology Centre, at IPEN/CNEN-SP. The irradiation system consists of an aluminium irradiation capsule, transfer lines, needle valves, ringed connections, quick connectors, manometer, vacuum system, dewar, lead shielding, storage and transport cylinders, among other components. The irradiation system was approved in the leakage and stability tests (bubble test, pressurization, evacuation and with leak detector equipment SPECTRON 600 T). In the experimental production obtaining 1.07×1011 Bq (2.9 Ci) of 41Ar, alanine dosimeters were distributed into various components of the irradiation system. In addition, exposure rates were determined in the lead shielding wall, in which the liquefied radioactive gas was concentrated, and in the storage and transport cylinders after 41Ar was transferred by the portable radiation meter Teletector® Probe 6150 AD-t/H.