DAIANE CRISTINI BARBOSA DE SOUZA

DAIANE CRISTINI BARBOSA DE SOUZA

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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.
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.
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.
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.
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
Estudo e desenvolvimento de metodologia para fixação de iodo radioativo em substrato polimérico para confecção de fontes utilizadas em braquiterapia
2014 - RODRIGUES, BRUNA T.; SOUZA, CARLA D.; BENEGA, MARCOS A.G.; SOUZA, ANDERSON S.; ROSTELATO, MARIA E.C.M.; ZEITUNI, CARLOS A.; TIEZZI, RODRIGO; PELEIAS, FERNANDO S.; SOUZA, DAIANE C.; SILVA, THAIS H.