CARLA DARUICH DE SOUZA

CARLA DARUICH DE SOUZA

(Fonte: Lattes)

Resumo

Bsc in Medical Physics from UNESP in Botucatu Compleated at IPEN, University of São Paulo: 1) Master's Degree: Comparison between methods for fixing iodine-125 on silver substrate for fabricating sources used in Brachytherapy / 2) PhD: Parameters for production of iodine-125 sources used in brachytherapy and "sandwich" doctorate: Washington State University - training in radiochemistry and organic chemistry / 3) Post doctorate: Production of nanosources for the treatment of cancer / 4) Project: Analysis of methods to obtain / produce nuclear material for use in a radioisotope thermoelectric generator (RTG)/ Advisor of the Professional Master's Degree in Radiation Technology in Health / Professor of the Professional Master Program in the disciplines Dosimetry for Radiotherapy and Radiotherapy Fundamentals / Professor of the Academic Master Program in the discipline TNA5805 - Brachytherapy: Fundamentals, Production, Application, Dosimetry and Quality Research Associate of KAERI - Korean Atomic Energy and Research Institute (Text obtained from the Currículo Lattes on October 6th 2021)

Formada em Física Médica pela UNESP em Botucatu Realizado no IPEN-USP/ SP: 1) Mestrado: Comparação entre métodos de fixação do iodo-125 em substrato de prata para confecção de fontes utilizadas em Braquiterapia / 2) Doutorado: Parâmetros para produção de confecção de fontes de iodo-125 utilizadas em Braquiterapia e Doutorado sanduíche: Washington State University - treinamento em radioquímica / 3) Pós doutorado: Produção de nanofontes para tratamento de câncer / 4) Projeto: Análise de formas de obtenção/produção do material nuclear para utilização em um gerador termoelétrico radioisotópico (RTG)/ Orientadora do Mestrado Profissional de Tecnologia das Radiações na Saúde/ Professora do Mestrado Profissional nas disciplinas Dosimetria para Radioterapia e Fundamentos de Radioterapia/ Professora do Mestrado Acadêmico na disciplina TNA5805 - Braquiterapia: Fundamentos, Produção, Aplicação, Dosimetria e Qualidade Research Associate do KAERI - Korean Atomic Energy and Research Institute (Texto extraído do Currículo Lattes em 06 out. 2021)

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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.
Waste management protocols for Iridium-192 sources production laboratory used in cancer treatment
2016 - ROSTELATO, MARIA E.C.M.; SOUZA, CARLA D. de; SOUZA, DAIANE C.B. de; ZEITUNI, CARLOS A.; TIEZZI, RODRIGO; COSTA, OSVALDO L. da; RODRIGUES, BRUNA T.; MOURA, JOÃO A.; FEHER, ANSELMO; SORGATTI, ANDERSON; MOURA, EDUARDO S. de; MARQUES, JOSE R. de O.; SANTOS, RAFAEL M. dos; KARAM JUNIOR, DIB
Introduction: Brachytherapy is a form of treatment that uses radioactive seeds placed in contact or inside the region to be treated, maximizing the radiation dose inside the targeted areas. Iridium-192 is being used in brachytherapy since 1955. It presents emission energy in the “therapy region” (370keV) and is easily produced in a nuclear reactor (191Ir (n, γ) → 192Ir). Wires are an iridium-platinum alloy with 0.36 mm diameter and they can be cut in any needed length. They can be used in several types of cancer. The linear activity is between 1 mCi/cm (37 MBq/cm) and 4 mCi/cm (148 MBq/cm) with variations of 10% in 50 cm maximum. This activity values classified the treatment and low dose rate (0,4 à 2 Gy/h). The propose of this work is to present a waste management system in a cancer treatment radioactive sources production laboratory. Methodology and 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 waste activity is adds to 8mCi (2.96x108 Bq) per wire. According to the CNEN-NN 6.08 standard, that presents the discharge levels, the limit is 1 kBq.kg-1 (2.7x10-5 mCi.kg-1). The radioactive waste generated during the I192 wires production has a weakly activity of 9.7 GBq.g-1. According to the standards, this activity is too high to be discarded into the environment. The waste must be managed following the ALARA principal using the R&R (retain e retard) system, that means, temporary storage and posterior discharge. Since every 4 months, maintenance is performed inside the hot cell used for production, the waste must be removed. Using the equation: 𝐴 = 𝐿 λ (1 − 𝑒−λt), the total calculated activity is 1.68 x 1016 Bq and 4.8 g mass at the end of each 4 months period. This amount is stored inside a shielding device that has 212.37 cm3 volume. The waste will take 9.8 years (calculated by 𝐴 = 𝐴0(𝑒−λt)) to decay to the discharge levels. To store 30 devices during 10 years, a space with 6,370 cm3 is necessary. The laboratory has enough space for this storage. Thus, the radioactive waste management can be performed through the R&R (retain and retard) system safely.
New core configuration for producing Iodine 125 seeds
2017 - RODRIGUES, B.T.; ROSTELATO, M.C.M.; SOUZA, C.D. de; ZEITUNI, C.; MOURA, E.S. de; SOUZA, D.B. de; TOZETTI, C.; RODRIGUES, B.
Purpose: Cancer is one of the most complex public health problems. Prostate cancer is the second most common among men. In prostate brachytherapy use Iodine-125, which is fixated on a silver substrate, then inserted and sealed in a titanium capsule. This work proposes a new source configuration using epoxy resin substrate. Methods: Comparation and analysis methods were used to define the methodology for combining iodine-125 in polymers. The parameters were immersion time, reaction type, concentration of the adsorption solution, specific activity of the radioactive solution, need for carrier and chemical form of radioactive iodine. Results: The methodology developed with an epoxy resin was very good. The final radioactive intake on the resin was higher than 80%. The immobilization of the radioactive solution occurred in the matrix, without any loss or deposition of undesirable materials on its surface, as evidenced by the smear test. The material maintains its integrity when autoclaved at 140 °C. The curing process of the resin was 40 minutes. With the value of the initial activity of the Iodine solution by mass (774.2 lCi/g), it was possible to calculate the immobilization efficiency Average of 680 lCi/g. The immersion test in distilled water at room temperature did not exceed the limit allowed by ISO 9978, which is 5 nCi (185 Bq), proof of no leakage. In a computational simulation by the Monte Carlo Method, PENELOPE, the simulations were consistent with the values adopted by the literature for the GE Healthcare model 6711, which shows the value of the dose rate constant as 0, 965 cGy.U-1.h-1. Conclusion: The effective method for combining iodine-125 in epoxy resin was determinated. The major advantage was the high efficiency percentage fixation, around 82,1 3,2%, and the simplicity and safety of the process.
Measurement of Iodine-125 radioactive solid waste derived from sources production laboratory for brachytherapy
2017 - SOUZA, D.B. de; ROSTELATO, M.C.M.; VICENTE, R.; ZEITUNI, C.; SOUZA, C.D. de; RODRIGUES, B.T.; MARQUES, J. de O.; CARVALHO, V.; BARBOSA, N.
Purpose: This study aims to present a solid waste management plan for the laboratory of radioactive sources production (LPFR), iodine-125 brachytherapy seeds, located at the Energy and Nuclear Research Institute (IPEN). After the implementation, it is expected to meet a demand of 8000 seeds per month. Methods: Waste from the production of Iodine-125 sources is classified as “Very Low Level Waste Disposal” (T1/2 ≤ 100 days) in the IAEA regulations. Despite that, they have levels of activity above the limits established in standard (CNEN 8.01) needing adequate management in order to guarantee the safety of the installation, operators and environment. The solid waste is generated in Glove box 1, were the fixation reaction (iodine-125 – core) takes place. The wastes from this production are absorbent papers and filters used in surface and air decontamination processes; glass vials, syringes and needles, used in the fixation reaction. Measures of mass, volume and values of activities generated over 5 years of production were performed for each glove box by estimating different scenarios throughout production (supplier switching, variation in activity by radioactive source, etc.). The concentration of activity was also determined in order to meet the criteria established in the standard for safe release of the waste. Results: The final volumes and activities calculated indicated that the laboratory has enough space for temporary storage until the release to the environment (thus not requiring treatment, transport, and another place for management). The data collected proved that a secure management system for radioactive waste within the facility is possible. Conclusion: The management proposed by this work was able to safely contemplate all stages of waste management. This data is indispensable for the construction and licensing of the laboratory.
Gamma spectrometry of iodine-125 produced in IEA-R1 nuclear reator, using HPGe detector and fixation into epoxy matrix disc
2019 - COSTA, OSVALDO L. da; SOUZA, DAIANE C.B. de; CASTANHO, FABIO G.; FEHER, ANSELMO; MOURA, JOÃO A.; SOUZA, CARLA D. de; OLIVEIRA, HENRIQUE B. de; MADUAR, MARCELO F.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.
Few places in the world produce iodine-125. In Brazil, the first production happened in nuclear reactor IEA-R1 located at Nuclear and Energy Research Institute – IPEN. To verify the quality of iodine-125 produced, because contaminants as iodine-126, caesium-134 and caesium-137 among others, may be produced in irradiation process, 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.
Nova metodologia para fixar iodo-125 em fontes radioativas RM resina epóxi
2017 - RODRIGUES, BRUNA T.; ROSTELATO, MARIA E.C.M.; SOUZA, CARLA D. de; TOZETTI, CINTIA A.; NOGUEIRA, BEATRIZ R.; SOUZA, DAIANE C.; ZEITUNI, CARLOS A.; MARQUES, JOSE R. de O.; SILVA, JOSE T. da
Introdução: O câncer de próstata é o mais comum entre os homens, aproximadamente 28,6%. A escolha do tipo de tratamento para o câncer da próstata deve considerar vários fatores como: tamanho e extensão do tumor, agressividade aparente (características patológicas), idade, saúde. A braquiterapia vem sendo utilizada em estágios iniciais e intermediários da doença porque é um tratamento seguro e efetivo para câncer prostático localizado. As sementes radioativas são colocadas em contato com ou dentro do órgão a ser tratado, permitindo que a dose de radiação seja liberada apenas no tumor alvo que proteja os tecidos circundantes saudáveis. As fontes podem ter diferentes formas e tamanhos, e a utilizada para câncer de próstata geralmente tem 4,5 mm de comprimento e 0,8 mm de diâmetro. Cerca de 80 a 120 sementes podem ser usadas por paciente. O Iodo-125 é o radioisótopo mais utilizado na braquiterapia da próstata, emite raios-X de 35,49 keV em 100% dos decaimentos, com energia média de 29 keV. Objetivos: Este trabalho propõe uma alternativa às sementes que já foram desenvolvidas, a fim de reduzir o custo. Desenvolvendo uma configuração de núcleo alternativa com o objetivo de aumentar o rendimento de iodo-125 fixado na matriz epoxídica, reduzindo assim o custo total. Resultados: Após produzidas as fontes, foi realizado teste de estanqueidade, com a fonte imersa em água destilada à temperatura ambiente. O resultado não excedeu o limite permitido pela norma ISO 9978 que é de 5 nCi (185 Bq) e o teste de esfregaço não indicou atividade no papel filtro. Conclusão: A fonte foi considerada estanque, após testes padrões, sem qualquer vazamento do material radiativo, viabilizando a matriz epóxi para confecção dos núcleos. Resultando em um método seguro e eficiente. Todos os resultados obtidos apresentaram um alto percentual de eficácia e melhor distribuição de atividade quando comparada às metodologias clássicas de núcleo de prata. As diferenças de eficiência entre núcleos foram causadas por flutuações estáticas do sistema de detecção e balança. A eficiência média dos núcleos foi 82,1 ± 3,2%
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.
Coatings of nanoparticles applied to brachytherapy treatments
2017 - GONZALEZ, ANDREZA A.D.C.C.; ROSTELATO, MARIA E.C.M.; SOUZA, CARLA D.; RODRIGUES, BRUNA T.; SOUZA, DAIANE C.B.; ZEITUNI, CARLOS A.; NOGUEIRA, BEATRIZ R.
Brazilian demand for iodine-125 seeds in cancer treatment after a decade of medical procedures
2017 - COSTA, OSVALDO L. da; SOUZA, DAIANE C.B. de; FEHER, ANSELMO; MOURA, JOAO A.; SOUZA, CARLA D.; OLIVEIRA, HENRIQUE B. de; PELEIAS JUNIOR, FERNANDO S.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.
Brazil radioactive sources production for cancer treatment
2016 - ROSTELATO, MARIA E.; SOUZA, CARLA D.; ZEITUNI, CARLOS A.; MOURA, JOAO A.; MARQUES, JOSE R.O.; COSTA, OSVALDO L.; FEHER, ANSELMO; RODRIGUES, BRUNA T.; SOUZA, DAIANE C.B. de; PELEIAS JUNIOR, FERNANDO S.; SORGATTI, ANDERSON; MOSCA, RODRIGO; MOURA, EDUARDO S. de; ABREU, RODRIGO T.; SOUZA, RAQUEL V. DE; NOGUEIRA, BEATRIZ R.
The modality, known as brachytherapy, was performed in Brazil by only a hand full of hospitals at an extremely high cost. For producing new sources, five major areas must be considered: 1) source production: nuclear activation and/or radiochemical reaction; 2) welding; 3) Quality control: leakage tests; 4) Dosimetry and metrology; 5) Operational procedures; 6) validation studies. To perform all steps, a multidisciplinary team works together to overcome difficulties. - Iridium-192 pellets: In Brazil there are 140 machines with pellets that replacement every 5 years. Our new production line has assembly, welding and quality control hot cells. - Iridium-192 wires: Produced since 1999. The wire is activated at IPENs IEA-R1 reactor for 30 hours with 5x1013 n/cm-2.s-1 neutron flux resulting in 192 mCi maximum activity. - Iridium-192 seed: New seed for ophthalmic cancer treatment. The irradiation device presented 90% activity homogeneity. We are still testing in-vivo. - Iodine-125 seeds: Largely used in low dose brachytherapy. I-125 binding yield achieved with our new reaction was 80%; Laser welding presented 70% efficiency. Approved in all leakage tests. - Other ongoing projects: Veterinary brachytherapy, Waste management, Radionecrosis healing with laser, calibrations sources production, linear accelerator calculations for hospitals, sources with polymeric matrix Our Iodine-125 seeds will be available in 2018. All other projects are advancing. We will continue to develop new products hoping to help the Brazilian population fight against cancer. For producing new sources, five major areas must be considered: 1) source production: nuclear activation and/or radiochemical reaction; 2) welding; 3) Quality control:eakage tests; 4) Dosimetry and metrology; 5) Operational procedures; 6) validation studies. To perform all steps, a multidisciplinary team works together to overcome difficulties