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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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.
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
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.
Comparison of the dosimetric parameters in linear accelerators with flattening filter-free (FFF) and flattening filter (FF)
2015 - SOUZA, ANDERSON S.; ROSTELATO, MARIA E.C.M.; ZEITUNI, CARLOS A.; MOURA, EDUARDO S.; RODRIGUES, BRUNA T.; SOUZA, DAIANE C.; TIEZZI, RODRIGO; SOUZA, CARLA D.; MELO, EMERSON R.; CARMARGO, ANDERSON R.; BATISTA, TALITA Q.
Assessment of the risks associated with iodine-125 handling production sources for brachytherapy
2015 - SOUZA, DAIANE C.B.; ROSTELATO, MARIA E.C.; VICENTE, ROBERTO; ZEITUNI, CARLOS A.; TIEZZI, RODRIGO; COSTA, OSVALDO L.; SOUZA, CARLA D.; PELEIAS JUNIOR, FERNANDO S.; RODRIGUES, BRUNA T.; SOUZA, ANDERSON S.; KARAM JUNIOR, DIB; BATISTA, TALITA Q.; MELO, EMERSON R.; CAMARGO, ANDERSON R.
Study of acid solution bonding in epoxy matrix for sealed radioactive sources production
2014 - BENEGA, MARCOS A.G.; NAGATOMI, HELIO R.; ROSTELATO, MARIA E.C.M.; TIEZZI, RODRIGO; RODRIGUES, BRUNA T.; PELEIAS JUNIOR, FERNANDO S.; SOUZA, CARLA D.; SOUZA, DAIANE C.C. de; SOUZA, ANDERSON S. de; SILVA, THAIS H. da