Evaluation of Radioactivity in Therapeutic Radiopharmaceutical Waste

Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while...

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Published inProgress in Medical Physics Vol. 35; no. 4; pp. 163 - 171
Main Authors Jo, Jung Ju, Lee, Su Hyoung, Ki, Beom Hoon, Ryu, Ho Jin, Kim, Tae Hwan, Kim, Gi Sub, Lee, Sang Kyu, Kim, Dong Wook, Kim, Kum Bae, Kim, Sangrok, Choi, Sang Hyoun
Format Journal Article
LanguageEnglish
Published 한국의학물리학회 31.12.2024
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ISSN2508-4445
2508-4453
DOI10.14316/pmp.2024.35.4.163

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Summary:Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I -131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels. Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions: These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices. KCI Citation Count: 0
Bibliography:https://www.progmedphys.org/journal/view.html?pn=current_issue&uid=952&vmd=Full
ISSN:2508-4445
2508-4453
DOI:10.14316/pmp.2024.35.4.163