Waste management protocols for Iridium-192 sources production laboratory used in cancer treatment
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2016
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INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION, 14th
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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.
Como referenciar
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. 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. Abstract... p. 2038-2038. Disponível em: http://repositorio.ipen.br/handle/123456789/31273. Acesso em: 30 Dec 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.