Prog Med Phys.  2024 Dec;35(4):163-171. 10.14316/pmp.2024.35.4.163.

Evaluation of Radioactivity in Therapeutic Radiopharmaceutical Waste

• Jo JJ
• Lee SH
• Ki BH
• Ryu HJ
• Kim TH
• Kim GS
• Lee SK
• Kim DW
• Kim KB
• Kim S
• Choi SH

• KMID: 2564155
• DOI: http://doi.org/10.14316/pmp.2024.35.4.163

Abstract

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.

Keyword

Radiopharmaceutical waste; Self-disposal; Nuclear medicine; Radioactivity; High-purity germanium detector

Figure

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  Fig. 1 A schematic diagram showing the measurement procedure.

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  Fig. 2 Types of Iodine-131-containing radioactive waste. (a) Plastic, (b) slippers, (c) tableware (spoon and chopsticks), and (d) towels.

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  Fig. 3 Types of waste containing Lutetium-177 and Actinium-225. (a) Combustible 1, (b) combustible 2, (c) needles and tubes, and (d) syringes.

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  Fig. 4 Measurement process of radiation dose rate and radioactivity. (a) Prediction of deadtime using survey meter. (b) High-purity germanium measurement using ziplock bags.

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  Fig. 5 HPGe peak analysis results. (a) I-131-containing combustibles, (b) Lu-177-containing vials, and (c) Ac-225-containing needles and tubes. HPGe, high-purity germanium; I-131, Iodine-131; Lu-177, Lutetium-177; Ac-225, Actinium-225.

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  Fig. 6 Iodine-131 measurement results.

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  Fig. 7 Measurement of Iodine-131 using slippers.

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  Fig. 8 Lutetium-177 measurement results.

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  Fig. 9 Actinium-225 measurement results.

Reference

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