JOÃO AUGUSTO MOURA

JOÃO AUGUSTO MOURA

(Fonte: Lattes)

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Possui graduação em Tecnologia em saúde pela Faculdade de Tecnologia de Sorocaba (2005). Mestrado em Tecnologia Nuclear pela Universidade de São Paulo (2009). Doutorado em Tecnologia Nuclear pela Universidade de São Paulo (2015). Tem experiência na área de Tecnologia Nuclear, com ênfase em produção de fontes para radioterapia. Atualmente trabalha em pesquisa e desenvolvimento no Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP). (Texto extraído do Currículo Lattes em 8 maio 2023)

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A proposal of process validation in the implementation of Good Manufacturing Practices in brachytherapy sources production
2021 - BAPTISTA, TATYANA S.; FEHER, ANSELMO; RODRIGUES, BRUNA T.; ZEITUNI, CARLOS A.; MOURA, JOÃO A.; ROSTELATO, MARIA E.C.M.
New laboratories for brachytherapy sources production are being implemented in our facility at IPEN, in São Paulo. A great challenge implementing a production laboratory is to comply with the Good Manufacturing Practices (GMPs), which involves process validation and all supporting activities such as cleaning and sanitization. Much more than compliance with regulatory guidelines, required for certification and inspections, a validation builds large process knowledge, provides possibilities for optimization and improvement, increasing the degree of maturity of all people involved and the quality system. The process validation results in a document that certifies that any procedure, process, equipment, material, operation, or system leads to the expected results. This work focused on the new laboratory, been assembled to produce small iodine-125 seeds. The process validation was performed three times for evaluation. The parameters evaluated in this study were: the source welding efficiency and the leakage tests results (immersion test). The welding efficiency does not have an established parameter, since is visually evaluated by the operator, and the leakage detection must be under 5 nCi / 185 Bq, accordingly with the ISO 9978. We observed values were average 79-87% production efficiency and leakage tests were under 5 nCi/seed. Although established values for the global efficiency aren’t available in the literature, the results showed high consistency and acceptable percentages, especially when other similar manufacturing processes are used in comparison (average 85-70% found in the literature for other similar metallic structures). Those values will be important data when drafting the validation document and to follow the Good Manufacturing Practices (GMPs).
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.
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.
Development of an automated system for the operation of an electron beam accelerator
2019 - SOMESSARI, S.L.; MOURA, J.A.; CALVO, W.A.P.
Electron beam accelerators are used in many applications, such as basic physical research, chemistry, medicine, molecular biology, microelectronics, agriculture and industry, among others. The majority of the accelerators have electrons from a hot tungsten filament and their energy is increased as it passes through an electric field in the vacuum chamber. For industrial purposes, the most common model is Dynamitron®. At IPEN-CNEN/SP, there is an electron beam accelerator Dynamitron® Type (Manufactured by RDI - Radiation Dynamics Inc., 1978) model DC1500/25/4. The technology applied was available in the 60´s and 70´s, but, nowadays is obsolete. Moreover, there are not original spare parts for this equipment any longer. The aim of this work is to develop a nationalized automated operation system for the accelerator, to replace the old equipment and allow extending the useful life of the accelerator for around ten years.
Waste management protocols for iridium-192 sources production laboratory used in cancer treatment in Brazil
2017 - ROSTELATO, M.E.C.M.; SOUZA, D.C.B.; SOUZA, C.D.; ZEITUNI, C.A.; VICENTE, R.; COSTA, O.L.; RODRIGUES, B.T.; MOURA, J.A.; FEHER, A.; MOURA, E.S.; MARQUES, J.R.O.; CARVALHO, V.S.; NOGUEIRA, B.R.
Objective: The iridium-192 wired sources production results in radioactive waste that needs to follow the guidelines. The aim of this study is to do a radioactive waste management of wastes from iridium-192 sources production laboratory used in cancer treatment in Brazil. Methods: The wire is acquired in an alloy form with 80% platinum and 20% iridium encapsulated with 100%. Electronic microscopy, X-ray fluorescence, and posterior iridium neutron activation (to determine contaminants) are performed to ensure quality. A 50-cm twisted wire is placed in an aluminum tube. The tube is sealed and place inside the reactor irradiator system and is left for decay during 30 hours to wait for the others undesired activation products to decay. The wire is prepared for treatment with 48 cm length with 192 mCi maximum activity. All the equipment use inside the hot cell must be calibrated every four months. All the waste must be removed from the hot cell. Results: The solid waste is previously characterized in the analysis phase. The contaminants are already known and they are insignificant due to their fast half-life. The iridium-192 half-life is 74.2 days, classified as very short half-life waste. The reminiscent activity is 8mCi. Conclusion: The radioactive waste generated during the I192 wires production is solid, was a short half-life and a weakly activity of 9.7 GBq.g-1. According to the standards, this activity is too high to be discarded into the environment (limit 10 Bq.g-1). The waste must be managed by the R&R (retain e retard) system.
Comparing different methods for radioactive iodine fixation intended for brachytherapy sources manufacture
2016 - 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. de
Brachytherapy, 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.
Study of the positioning influence in the water activity measurement during leak test of iodine-125 seeds
2015 - MOURA, JOAO A.; FEHER, ANSELMO; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.; CALVO, WILSON A.P.; COSTA, OSWALDO L.; SOUZA, CARLA D.; JUNIOR, DIB K.; CAMARGO, ANDERSON R.
Desenvolvimento da metodologia para sintese do poli-)acido latico-co-acido glicolico) para utilização na produção de fontes radioativas
2015 - PELEIAS JUNIOR, FERNANDO dos S.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.; FECHINE, GUILHERMINO J.M.; SOUZA, CARLA D. de; MATTOS, FABIO R. de; MOURA, EDUARDO S. de; MOURA, JOAO A.; BENEGA, MARCOS A.G.; FEHER, ANSELMO; COSTA, OSVALDO L. da; RODRIGUES, BRUNA T.
A Organização Mundial da Saúde (OMS) relata o câncer como uma das principais causas de morte no mundo. Uma modalidade de tratamento que vem sendo bastante utilizada no tratamento do câncer de próstata é a braquiterapia, que consiste na introdução de sementes com material radioativo no interior do orgão. Sementes de Iodo-125 podem ser inseridas soltas ou em cordas poliméricas fabricadas a partir do (poli(ácido lático-co-ácido glicólico)) (PLGA). Foi proposto neste trabalho, o estudo e desenvolvimento da metodologia de síntese do biopolímero PLGA. Os resultados obtidos demonstram que, através da metodologia utilizada, foi possível determinar os melhores parâmetros de reação (tempo e temperatura) para o PLGA na proporção 80/20 (lactídeo/glicolídeo). Com uma temperatura de 110 °C e tempo de reação 72h o rendimento da reação é superior a 90%. Os valores de massas moleculares obtidas entre os testes, ainda são baixos quando comparados com os valores obtidos por outros autores na literatura. Novos testes estão sendo conduzidos, utilizando dímeros preparados no laboratório. Testes substituindo o vácuo por uma atmosfera de nitrogênio também estão sendo realizados. Essas duas substituições podem aumentar o valor final da massa molecular do polímero. Em relação à caracterização, as técnicas utilizadas confirmaram a estrutura esperada do polímero.
A study about the measurement method of the homogeneity of radioactivity along an iridium-192 wire used in brachytherapy
2014 - COSTA, OSVALDO L.; CALVO, WILSON A.P.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.; MOURA, JOAO A.; FEHER, ANSELMO; SOUZA, CARLA D.; SOMESSARI, SAMIR L.
The Nuclear and Energy Research Institute has produced, since 1998, iridium-192 wires used in low dose rate brachytherapy. In the paper the authors studied the influence of wire profile on the homogeneity distribution of radioactivity of iridium-192 along the wire. The authors propose the improvements in the quality control procedure that will provide more accurate measurement data and suggest changes in control devices.
Development and production of radioactive sources used for cancer treatment in Brazil
2008 - ROSTELATO, MARIA E.C.M.; RELA, PAULO R.; ZEITUNI, CARLOS A.; FEHER, ANSELMO; MANZOLI, JOSE E.; MOURA, JOAO A.; MOURA, EDUARDO S.; SILVA, CONSTANCIA P.G.