DAIANE CRISTINI BARBOSA DE SOUZA

DAIANE CRISTINI BARBOSA DE SOUZA

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Opening the Goiânia accident unburied waste packages
2021 - TESSARO, ANA P.G.; GERALDO, BIANCA; SOUZA, DAIANE C.B. de; SMITH, RICARDO B.; VICENTE, ROBERTO
The year 2017 marks 30 years since the radiological accident in Goiânia, Brazil, which resulted from the leakage of Cs-137 from a teletherapy equipment. The contaminated material collected during the response to the accident was disposed of in Abadia de Goiás, about 20 km from Goiânia. However, in the initial 15-day period before the authorities were notified, contaminated paper bales and scrap metal were sold and transported to material recycling facilities in the State of São Paulo, one thousand kilometers away. These materials were later collected in steel boxes and drums, and stored in the intermediate waste storage facility of the Nuclear and Energy Research Institute - IPEN, in São Paulo. The objective of this paper is to describe the work performed to check the present condition of the paper bales waste boxes, reassess the reported Cs-137 activities, and evaluate possible treatment methods that can be applied to reduce the volume of waste. Prospective waste treatment methods are discussed.
Essays on nuclear energy and radioactive waste management
2021 - TESSARO, ANA P.G.; GERALDO, BIANCA; SOUZA, DAIANE C.B. de; ROMERO, FERNANDA; BISURI, INDRANIL; MARUMO, JULIO T.; CHEBERLE, LUAN T.V.; SACHDEVA, MAHIMA; ROSA, MYCHELLE M.L.; ROLINDO, NATALIE C.; SMITH, RICARDO B.; VICENTE, ROBERTO; SALVETTI, TEREZA C.
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.
O impacto do hipofracionamento de dose na saúde da mulher brasileira acometida com câncer de mama
2019 - SUKADOLNIK, MIKAELL P.; SILVA, RODRIGO A. da; SOUZA, DAIANE C.B. de; MUNOZ, BERGMAN N.S.
Atualmente, os tratamentos mais utilizados para o combate ao câncer são cirurgia, quimioterapia e radioterapia, o aperfeiçoamento desses métodos são cada vez mais solicitados. Diante deste cenário de crescente incidência do câncer de mama há a necessidade de que os serviços de radioterapia se adaptem à grande demanda de pacientes. Estudos têm apontado que o hipofracionamento pode ser uma técnica promissora para a redução da quantidade de sessões por paciente, consequentemente diminuindo o tempo total de tratamento. O hipofracionamento de dose é uma técnica utilizada na radioterapia, seu escopo é reduzir a quantidade de sessões por paciente, sem comprometer o tratamento. A proposta deste estudo foi destacar o impacto do uso dessa técnica no câncer de mama no Brasil, a fim de que os profissionais envolvidos estejam efetivamente bem preparados para utilizar essa técnica com excelência, tratando um número maior de pacientes em um período menor de tempo sem diminuir a qualidade da terapia.
Caracterização de embalados de rejeitos radioativos utilizando Microshield
2019 - SILVA, RODRIGO A. da; SUKADOLNIK, MIKAELL P.; TESSARO, ANA P.G.; SOUZA, DAIANE C.B. de; VICENTE, ROBERTO
Na extração de petróleo, há presença significativa de material radioativo de origem natural e, por isso, as empresas que realizam esse trabalho devem atender as normas de proteção radiológica estabelecidas pela Comissão Nacional de Energia Nuclear (CNEN). Determinar a concentração radioisotópica em rejeitos radioativos é um passo fundamental no processo de caracterização dos rejeitos e é essencial no tratamento, no transporte e na eliminação deles. Este estudo consistiu na utilização de medidas das taxas de dose e cálculos para estimativa do conteúdo radioativo presente em tambores com rejeitos provenientes da indústria de petróleo. Foi utilizado o programa para cálculo de blindagem Microshield. Os principais resultados obtidos foram os valores de taxa de dose e a espectrometria de emissão gama. O método baseado na medição das taxas de exposição em torno de embalados fornece boas aproximações quando as informações sobre emissores gama presentes nos embalados de rejeitos são obtidos por espectrometria gama.
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.
Desenvolvimento de um método para gerenciamento de rejeitos radioativos no laboratório de produção de fontes de iodo-125 utilizadas em braquiterapia
2018 - SOUZA, DAIANE C.B. de
A braquiterapia é um tratamento clínico que consiste na aplicação de fontes radioativas seladas em certos tipos de tumores. Atualmente, está em fase de implantação o laboratório para produção de fontes de 125I a fim de nacionalizar a produção de fontes para reduzir os custos na sua aplicação e atender a demanda da população brasileira. A tese defendida neste trabalho é o desenvolvimento de um método para o gerenciamento de rejeitos radioativos que serão gerados ao longo da produção dessas fontes. A metodologia aplicada consistiu na criação de etapas de gerenciamento de rejeitos radioativos aplicadas ao 125I que contemplasse o gerenciamento na própria instalação produtora. Os rejeitos radioativos que serão gerados ao longo de todo processo de fabricação das fontes de 125I serão produzidos dentro de três células estanques, localizadas dentro do laboratório. Para cada um dos cenários foram relacionados os rejeitos sólidos, líquidos e gasosos gerados em cada uma das três células de produção. Para rejeitos sólidos e líquidos foram estimados: volume, massa, taxa de entrada no depósito inicial e tempo para liberação em meio ambiente. Para rejeitos gasosos foi estimado: taxa de volatilização do 125I e metodologia para medição dos filtros de carvão ativado. Os resultados apresentados permitem concluir que o laboratório tem condições de realizar o gerenciamento dos rejeitos que produzirá. Implantar um sistema de gerenciamento dentro do próprio laboratório, aperfeiçoará as atividades rotineiras e o licenciamento junto a CNEN.