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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Radioactive seed localization for nonpalpable breast lesions
2024 - FERREIRA, HORTENCIA H.J.; SOUZA, CARLA D. de; POZZO, LORENA; RIBEIRO, MARTHA S.; ROSTELATO, MARIA E.C.M.
Background: This study is a systematic review with meta-analysis comparing radioactive seed localization (RSL) versus radio-guided occult lesion localization (ROLL) and wire-guided localization (WGL) for patients with impalpable breast cancer undergoing breast-conserving surgery and evaluating efficacy, safety, and logistical outcomes. The protocol is registered in PROSPERO with the number CRD42022299726. Methods: A search was conducted in the Embase, Lilacs, Pubmed, Scielo, Web of Science, and clinicaltrials.gov databases, in addition to a manual search in the reference list of relevant articles, for randomized clinical trials and cohort studies. Studies selected were submitted to their own data extraction forms and risk of bias analysis according to the ROB 2 and ROBINS 1 tools. A meta-analysis was performed, considering the random effect model, calculating the relative risk or the mean difference for dichotomous or continuous data, respectively. The quality of the evidence generated was analyzed by outcome according to the GRADE tool. Overall, 46 articles met the inclusion criteria and were included in this systematic review; of these, 4 studies compared RSL and ROLL with a population of 1550 women, and 43 compared RSL and WGL with a population of 19,820 women. Results: The results showed that RSL is a superior method to WGL in terms of surgical efficiency in the impalpable breast lesions’ intraoperative localization, and it is at least equivalent to ROLL. Regarding security, RSL obtained results equivalent to the already established technique, the WGL. In addition to presenting promising results, RSL has been proven to be superior to WGL and ROLL technologies.
Synthesis, in vitro testing, and biodistribution of surfactant-free radioactive nanoparticles for cancer treatment
2022 - SOUZA, CARLA D. de; BARBEZAN, ANGELICA B.; ROSERO, WILMMER A.A.; SANTOS, SOFIA N. dos; CARVALHO, DIEGO V. de S.; ZEITUNI, CARLOS A.; BERNARDES, EMERSON S.; VIEIRA, DANIEL P.; SPENCER, PATRICK J.; RIBEIRO, MARTHA S.; ROSTELATO, MARIA E.C.M.
New forms of cancer treatment, which are effective, have simple manufacturing processes, and easily transportable, are of the utmost necessity. In this work, a methodology for the synthesis of radioactive Gold-198 nanoparticles without the use of surfactants was described. The nuclear activated Gold-198 foils were transformed into H198AuCl4 by dissolution using aqua regia, following a set of steps in a specially designed leak-tight setup. Gold-198 nanoparticles were synthesized using a citrate reduction stabilized with PEG. In addition, TEM results for the non-radioactive product presented an average size of 11.0 nm. The DLS and results for the radioactive 198AuNPs presented an average size of 8.7 nm. Moreover, the DLS results for the PEG-198AuNPs presented a 32.6 nm average size. Cell line tests showed no cytotoxic effect in any period and the concentrations were evaluated. Furthermore, in vivo testing showed a high biological uptake in the tumor and a cancer growth arrest.
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.
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.
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.
Efficiancy of hydrogen peroxide for cleaning production areas and equipments in the Laboratory for Brachyterapy Sources Production
2017 - BAPTISTA, T.; ROSTELATO, M.C.M.; ZEITUNI, C.; PERINI, E.A.; SOUZA, C.D. de; MARQUES, J. de O.; NOGUEIRA, B.R.; ANGELOCCI, L.V.
Purpose: A great challenge in the brachytherapy sources production is to fulfill the Good Manufacturing Practices (GMPs) requirements, involving the process validation and of all supporting activities such as cleaning and sanitization. The increasingly strict requirements for quality assurance system, with several norms, normative resolutions and rules that must follow both medical products and radiochemical requirements, has led to a constant validation concerns. The main goal of GMP is to reduce inherent risks such as product contamination with microorganisms and cross-contamination. Methods: In the Laboratory for Brachytherapy Sources Production it was established a cleaning program for cleanrooms and hot cells using a hydrogen peroxide solution (6%). This work aims to assess the effectiveness of this cleaning agent in reducing and/or eliminating microbial load into the cleanrooms and equipments to acceptable levels in accordance with the current legislation. Results: The analysis was conducted using the results of the environmental monitoring program with settling contact plates in cleanrooms after the cleaning procedures. Furthermore, it was possible to evaluate the action of the sanitizing agent on the microbial population at the equipment and cleanrooms’ surfaces. It was also evaluated the best way to accomplish the cleaning program considering the dosimetry factor in each production process, hence the importance of radiological contamination. All the following environmental monitoring procedures presented satisfactory results, showing that the cleaning procedures was able to reduce and maintain the acceptable levels of viable and non-viable particles for the cleanroom classification (ISO 5 and ISO 7). The cleaning process with this sanitizer (hydrogen peroxide) can be performed quickly right before the production; allowing the production of brachytherapy sources without after use residues. Conclusion: This data will help the production of a clean and reliable product.
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.
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.