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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Improvements in the quality control of iridium-192 wire used in brachytherapy
2011 - COSTA, OSVALDO L.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.; MOURA, JOÃO A.; FEHER, ANSELMO; MOURA, EDUARDO S.; SOUZA, CARLA D.; SOMESSARI, SAMIR L.
Brachytherapy is a method used in the treatment of cancerous tumors by ionizing radiation produced by sources introduced into the tumor area, this method seeks a more direct attack to the tumor, thereby maximizing the radiation dose to diseased tissue while minimizing the dose to healthy tissues (1). One of the radionuclides used in brachytherapy is iridium-192. The Radiation Technology Center (CTR) of the Nuclear and Energy Research Institute (IPEN) has produced commercially, since 1998, iridium-192 wires used in low dose rate (LDR) brachytherapy (2). To produce this radionuclide, firstly a iridium-platinum wire is irradiated in the nuclear reactor IEA-R1 for 30 hours with a neutron flux of 5 x 1013 ncm-2s-1, the wire is left to decay by 30 days to remove the main contaminants and then goes through a quality control before being sent to the hospital. In this quality control is checked the radiation homogeneity along each centimeter of the wire (3). To implement this procedure is used a device consisting of an ionization chamber surrounded by a lead shield with a small 1 cm wide slit, linked to the ionization chamber is a voltage source and a Keithley 617 electrometer, 2 minutes is the range used to measure the charge by the electrometer. The iridium wire is considered in accordance when there is no variation greater than 5% between the average measures and the maximum and minimum values. However, due to design features of the measurement system, the wire may appear to the detector through the slit in larger sizes than the ideal, improperly influencing the final quality control. This paper calculates the difference in size of these variations in profile and their influence on the final count, it compares the actual values obtained and describes the improvements made in quality control procedures that provided more accurate measurement data, analyzes the results and suggests changes in devices aimed at further improving the quality control of iridium-192 wires produced at IPEN and used in hospitals in Brazil.
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 methodology for binding Iodine-125 onto silver for brachytherapy sources manufacture
2017 - SOUZA, C.D. de; ROSTELATO, M.C.M.; CARDOSO, R.M.; ARAKI, K.; MOURA, J.
Purpose: Cancer is a major health care problem in Brazil and the world. The Brazil’s National Institute for Cancer estimates around 60,000 new prostate cancer cases for 2017. We are assembling a laboratory for production of iodine-125 sources used in prostate brachytherapy in Brazil, since the imported treatment is extremely expensive, thus only available in the private healthcare sector. There are several challenges when developing a laboratory to produce radioactive sources. From choosing a prototype to radiation safety, the task is enormous. The whole production line is full of new process and innovations. Among those, a new chemical reaction that deposit iodine-125 onto silver (core) was developed. This paper presents a new reaction for binding iodine-125 into a silver core. The fixation percentage was calculated by measuring the activity in an ionization chamber. This methodology will be implemented at the iodine-125 sources manufacture laboratory. Methods: Silver cores are washed with an etching solution (100% sulfuric acid) for 5 minutes with sonication. The cores were then placed in sodium sulfate for at least 3 days. They went from a silver matte to a black color. The reaction was allowed to proceed overnight. Each core was individually measured. Results: The yield was 69.2% 7.1%. Considering the silver attenuation is around 20% the results were consider satisfactory. Conclusion: By maximize the reaction yield, we will be able to generate a less costly product that will be available through our public healthcare.
Methodology for in vivo dosimetry using TLD-100 for radiotherapic treatment
2017 - RODRIGUES, B.T.; SOUZA, P.D. de; SOUZA, C.D. de; ROSTELATO, M.C.M.; ZEITUNI, C.; NOGUEIRA, B.R.; MARQUES, J. de O.; SOUZA, A.S. de
Cancer is a public health problem that affects approximately 27 million people worldwide. The most common type in Brazil among men is prostate cancer with 61 thousand cases. There are two forms of radiotherapy treatments that can be used: teletherapy and brachytherapy. Before starting the teletherapy treatment, a planning is done that makes the acquisition of the anatomical information of the patient to then classify the areas of interest. Dosimetry is performed as a quality control to ensure that the calculated dose is equal to that received by the patient. In vivo dosimetry acts as an independent measurement and this work aims at comparing the dosimetry performed using thermoluminescent dosimeters (LiF: Mg, Ti - TLD - 100) with dose values calculated in the planning system (TPS). Methods: All dosimeters were prepared to be used in an anthropomorphic phantom. A selection of dosimeters, 50 micro TLD’s, selected after heat treatment, were then irradiated and a reading was made. A case planned by TPS was selected and compared the dosimetry performed in an anthropomorphic phantom for the same case. Results: All values obtained were within the deviation ( 5%) allowed by the protocol. The results of this work will help to implement a new quality program in the Radiotherapy Service at Hospital das Cl ınicas de S~ao Paulo. Conclusion: The accurate dosimeter selection provided a feasible and reliable evaluation that enabled the comparison.
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.
Gold nanoparticle applied to brachytherapy
2019 - GONZALEZ, ANDREZA A.D.C.C.; SOUZA, CARLA D.; ARCOS, WILMER A.; RODRIGUES, BRUNA T.; DOMINGUES, PAULO R.; SPINOSA, TATYANA B.; ROSTELATO, MARIA E.C.M.
Cancer is a global public health problem, that consists in a disease is characterized by the uncontrolled growth of anomalous cells that impair the functioning of the body. One of the treatments for cancer is the brachytherapy. This technique a non-invasive treatment in which the radiation is placed close or in contact with the region to be treated, brachytherapy may save the healthy tissues and consequently reduces the amount of side effects. An unexplored strand is nanobrachytherapy, that unites the advantages of brachytherapy with the small size in the nanoparticle (NP), resulting in an even less invasive treatment. Nanotechnology is the science that studies the properties of nanometric materials with the aim of creating new materials with different properties of interest. In view of the synthesis of the NP and their applicabilities, there is a fundamental role that is made to coatings, which have the function of avoiding the aggregation of particles, stabilize and also control their functional properties. Besides being able to add molecules of interest, such as antibiotics and anti-inflammatories. Among the range of coatings, the most outstanding are polyethylene glycol (PEG). PEG improves the surface properties of NP and presents high stability under biomedical conditions. The NP have their size controlled, which facilitates their penetration into the vasculature, in addition to being a non-toxic coating. After the synthesis of gold nanoparticles (Au-NP) was developed, PEG were successfully incorporated into the surface. Incorporation was confirmed by DLS, FT-IR and HRTEM.
New gold-198 nanoparticle synthesis to be used in cancer treatment
2019 - SOUZA, CARLA D. de; ZEITUNI, CARLOS A.; ROSERO, WILMMER A.A.; NOGUEIRA, BEATRIZ R.; ROSTELATO, MARIA E.C.M.
Gold nanoparticles (NPs) have been intriguing scientists for over 100 years. Recently, they have been studied for new applications such as cancer treatment. Although the synthesis of gold nanoparticles is extensively reported, in the majority of cases the methodology is confused and/or not clear. We describe a new synthesis methodology for radioactive gold‐198 NPs. Gold-198 was activated in IPEN IEA-01 nuclear reactor to a neutron flux with 1013 order. After that, chloroauric acid (HAuCl4) was formed by dissolving the radioactive gold with aqua regia and performing repeated heating cycles. 0.1 mM HAuCl4 containing 100 μL of 1 M NaOH was prepared in a flask equipped with a reflux condenser. The solution was brought to boil and stirred with a PTFE‐coated magnetic stir‐bar. Then 5 mL of sodium citrate was rapidly added. The reaction turns from light yellow to clear, black, dark purple until the solution attained a wine‐red color (2–3 min). Dynamic light scattering (DLS) confirmed 8 nm particles. The presence of gold‐198 (197.968 g/mol; half‐life: 2.69517; decay mode: β‐; average energy: 1.3723 MeV) was confirmed by an ORTEC HPGe detector. DLS was performed after complete decay confirming the 8 nm diameter maintenance. We were able to achieve radioactive gold‐198 NPs and are performing further studies such as: coating reactions, in‐vitro and in‐vivo studies.
Gold nanoparticles stabilized with gum arabic for cancer treatment
2019 - ROSERO, WILMMER A.A.; NOGUEIRA, BEATRIZ R.; SOUZA, CARLA D. de; GONZALEZ, ANDREZA A.D.C.C.; BARBEZAN, ANGELICA B.; ZEITUNI, CARLOS A.; ROSTELATO, MARIA E.C.M.
Cancer is a group of diseases characterized by uncontrolled growth and abnormal spread of cells. The number of deaths due to cancer is higher than the ones caused by AIDS, tuberculosis and malaria combined. Among the different options of cancer treatment radiotherapy (teletherapy and brachytherapy) sta nds out. The presence of gold nanoparticles (AuNPs) may enhance energy deposition for teletherapy treatment. The use of nanoparticles for brachytherapy have been studied, and AuNPs is a good option once they can easily permeate tumor vasculature and remain in tumors. However, the tumor uptake of AuNPs may be significantly reduced due the attenuation with the formation of the protein coronas. The objective of this work is present the functionalization of AuNPs with arabic gum (GA). GA is a biocompatible, non toxic, water soluble, natural gum obtained from Acacia senegal tree. In this study, a synthesis of gold nanoparticles (AuNPs), based on Turkevich method, using citrate (NaCit) solution as reducing agent and a HAuCl4 solution, under vigorously stirring and boiling temperature, going from a light yellow to a wine red in three minutes. The functionalization of the nanoparticles was performed with Arabic gum solutions, in three different concentrations , which were a dded under stirring to the AuNPs already obtai ned. Samples were characterized to measure the size of the samples. Lower concentrations o GA in the solution presented smaller coated particles (up to 45 nm).
New gold-198 nanoparticle synthesis to be used in cancer treatment
2018 - SOUZA, C.D. de; ROSTELATO, M.C.M.; ZEITUNI, C.; GONZALEZ, A. del C.C.; NOGUEIRA, B.R.
Parâmetros para produção de fontes de iodo-125 utilizadas em Braquiterapia
2016 - SOUZA, CARLA D. de
Como o diagnóstico do cancer de próstata está cada vez mais eficiente e cânceres em pacientes cada vez mais jovens estão sendo descobertos, a necessidade de desenvolvimento de tratamentos que provoquem menores efeitos colaterais é muito grande. Além disso, tratamentos rápidos, com pouca dor e eficientes são de extremo interesse também para os pacientes com idade avançada. Com a finalidade de diminuir custos e disponibilizar o tratamento para mais homens, o IPEN está construindo um laboratório para a fabricação de fontes radioativas para o tratamento braquiterápico. Essas fontes são inseridas diretamente dentro do câncer e utilizam a radiação do iodo-125 para destruir o tumor. Como a reprodução de técnicas existentes seriam custosas, novos métodos para fixação do Iodo-125 no núcleo de prata dessa semente devem ser desenvolvidas. Este trabalho apresenta dois métodos inéditos. O primeiro, desenvolvido em parceria com o Instituto de Química da USP, utilizou a solução piranha para decapar a superfície e o nitrato de ferro III para remover um elétron da prata metálica. O iodo-125 adere na superfíce com 37,76% de eficiência. No segundo métodos três variações foram apresentadas inspiradas em conceitos utilizados por joalheiros: núcleos de prata escurecidos pelo talco comum, núcleos escurecidos com prata e tiossulfato de sódio e núcleos escurecidos somente com tiossulfato de sódio. Os resultados foram 19,17%, 53,39% e 71,70% de eficiência, respectivamente. Outros aspectos da reação foram discutidos: pH da reação, frasco utilizado no experimento, presença de luz, técnicas de medição, volume da reação, segurança e pureza química. As modificações na superfície foram visualizadas por MEV e analizadas por EDX. Como resultado, uma nova metodologia para produção de sementes de iodo-125 foi desenvolvida e analisada.