Detection, identification, and management of alpha-emitting radioactive waste in scrap metal: a case study from Kosovo

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ID: 329143
2026
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Abstract
Abstract Detection and management of alpha (α)-emitting radioactive sources in scrap metal present a significant challenge for radiological safety, particularly in countries lacking infrastructure for the final disposal of radioactive waste. This paper presents a case study from Kosovo addressing the detection, identification, dose measurement, and isolation of an alpha-emitting radioactive source discovered in scrap metal. Identification was performed using portable radiation survey instruments and gamma spectrometry, confirming the presence of thorium-232 and uranium-232. Measurements indicated a count rate of ~2000 cps and a maximum ambient dose rate of 6.51 μSv/h measured at an approximate distance of 5 cm from the radioactive source prior to isolation and concrete filling. To reduce exposure and contamination risks, the source was isolated in a 200-L metal drum filled with reinforced concrete. Dose rate mapping performed before and after isolation demonstrated a significant reduction in radiation levels, with a maximum reduction factor of 4.86, indicating a measurable reduction in ambient dose rate following temporary isolation.
Reference Key
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Authors Blerim Rrakaqi, Ylli Kaçiu, Shyqeri Dumani, Njomza Elezaj
Journal Radiation protection dosimetry
Year 2026
DOI
10.1093/rpd/ncag080
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