ROSTELATO, MARIA E.C.M.SOUZA, CARLA D. deSOUZA, DAIANE C.B. deZEITUNI, CARLOS A.TIEZZI, RODRIGOCOSTA, OSVALDO L. daRODRIGUES, BRUNA T.MOURA, JOÃO A.FEHER, ANSELMOSORGATTI, ANDERSONMOURA, EDUARDO S. deMARQUES, JOSE R. de O.SANTOS, RAFAEL M. dosKARAM JUNIOR, DIBCLEMENT, CHRISTOPHERVALENTIN, JACKOGINO, HARUYUKIFOOTE, DEVONREYJAL, JULIEOMAR-NAZIR, LAILA2020-06-092020-06-09ROSTELATO, 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. Waste management protocols for Iridium-192 sources production laboratory used in cancer treatment. In: CLEMENT, CHRISTOPHER (ed.); VALENTIN, JACK (ed.); OGINO, HARUYUKI (ed.); FOOTE, DEVON (ed.); REYJAL, JULIE (ed.); OMAR-NAZIR, LAILA (ed.). In: INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION, 14th, May 9-13, 2016, Cape Town, South Africa. <b>Abstract...</b> p. 2038-2038. Disponível em: http://repositorio.ipen.br/handle/123456789/31273.http://repositorio.ipen.br/handle/123456789/31273Introduction: 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.2038-2038openAccesswaste managementradioactive materialsradioactive wastesneoplasmstherapyiridium 192radioactive waste managementsealed sourcesbrachytherapyResumo de eventos científicos0000-0001-5989-72870000-0002-7303-67200000-0003-2943-6097https://orcid.org/0000-0002-5054-0799https://orcid.org/0000-0002-7303-6720http://orcid.org/0000-0003-1335-8864https://orcid.org/0000-0003-2943-6097