ANSELMO FEHER
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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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Artigo IPEN-doc 24717 Irradiation system for production of gaseous radioisotopes used as tracers in industrial process measurements2018 - 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.Artigo IPEN-doc 22420 Comparing different methods for radioactive iodine fixation intended for brachytherapy sources manufacture2016 - SOUZA, CARLA D.; ROSTELATO, MARIA E.C.M.; ZEITUNI, CARLOS A.; PELEIAS JUNIOR, FERNANDO S.; BENEGA, MARCOS A.G.; MOURA, JOAO A.; FEHER, ANSELMO; COSTA, OSVALDO L.; TIEZZI, RODRIGO; RODRIGUES, BRUNA T.; SILVA, THAIS H. da; SORGATTI, ANDERSON; SOUZA, DAIANE C.B. deBrachytherapy, a method of radiotherapy, is being extensively used in the early and intermediate stages of the illness. In this treatment, radioactive seeds are placed inside or next to the area requiring treatment, which reduces the probability of unnecessary damage to surrounding healthy tissues. Currently, the radioactive isotope iodine-125, fixated on silver substrate, is one of the most used in prostate brachytherapy. The present study compares several deposition methods of radioactive iodine on silver substrate, in order to choose the most suitable one to be implemented at the laboratory of radioactive sources production of IPEN. Three methods were selected: method 1 (test based on electrodeposition method, developed by David Kubiatowicz) which presented efficiency of 65.16%; method 2 (chemical reaction based on the method developed by David Kubiatowicz - HCl) which presented efficiency of 70.80%; method 3 (chemical reaction based on the method developed by Dr. Maria Elisa Rostelato) which presented efficiency of 55.80%. Based on the results, the second method is the suggested one to be implemented at the laboratory of radioactive sources production of IPEN.Artigo IPEN-doc 15791 Analysis of the necessary radioprotection procedures in manufacture of iodine-125 sources used in brachytherapy: A preliminary study2011 - SOUZA, CARLA D.; ROSTELATO, MARIA E.C.M.; ZEITUNI, CARLOS A.; MOURA, JOAO A.; MOURA, EDUARDO S.; FONSECA, KATIA; FEHER, ANSELMOArtigo IPEN-doc 19641 Leakage test methodology development in iodine-125 seeds production2013 - MOURA, JOAO A.; SOUZA, CARLA D. de; ROSTELATO, MARIA E.C.M.; MOURA, EDUARDO S. de; SPRENGER, FRANCISCO E.; NAGATOMI, HELIO R.; ZEITUNI, CARLOS A.; FEHER, ANSELMO; MANZOLI, JOSE E.Brachytherapy using iodine-125 seeds has been used in prostate cancer treatment. In the quality control routine during seed production, leakage tests are taken to detect any leakage of radioactive material from inside the titanium shield, avoiding patient contamination. Leakage tests are carried out according to the International Standard Organization e Radiation protection e sealed radioactive sources e ISO 9978. This standard recommends different methods of essay applied to radioactive seeds. The aims of this work were the study of the different leakage test methods applied to radioactive seeds recommended by the ISO 9978 and the choice of the appropriate method to be used in the seeds production. The authors evaluated five different immersion methods to detect leakage, following the standard guidance, and in some case exceeding its requirement. One hundred iodine-125 seeds were intentionally cuted, causing the release of its content. Each immersion method was applied to twenty seeds. After the immersion period, the resulting liquid activity was measured. The activity values measured in the immersion liquid indicated best results with distilled water as immersion liquid and with the application of ultrasound to the bath. The temperature of the bath ranged from 20 C to 70 C and the immersion time ranged from 30 min to 24 h. In this experiment, the use of scintillator liquid as immersion liquid was not effective to detect the leakage. The results allow the authors to choose the best methods to be applied in the production routine, to detect leakage in the seeds. The choice of the method will also depend on the production rhythm for schedule. In a moderate production rate, the test at 20 C and 24 h immersion may be used. In a fast production rhythm, the shortest test 50 C or 70 C should be used.