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    Assessment of extremity dose for medical staff involved in positron emission tomography/computed tomography imaging: Retrospective study
    (Lippincott Williams & Wilkins, 2023) Erdemir, Rabiye Uslu; Abuzaid, Mohamed Mahmoud; Cavli, Baris; Tekin, Huseyin Ozan; Elshami, Wiam
    There has been an increase in positron emission tomography (PET)/computed tomography (CT) imaging procedures, and medical workers involved in PET/CT are at increased risk of occupational exposure. Data on extremity dose exposure are limited globally. The current study aimed to evaluate the occupational radiation dose for extremities for medical workers (nurses, radiographers/radiologic technologists, and nuclear medicine physicians) working in PET/CT scanners at 5 large hospitals in Turkey. Optically stimulated luminescence (OSL) and Thermoluminescent dosimeter (TLD) ring dosimeters were used to measure equivalent dose values. Hospitals 1, 2, and 5 used OSL, and 3 and 4 used TLD. A total of 502 readings were obtained from 55 workers. In millisievert (mSv), the average annual effective dose for all workers was 14.5 +/- 17.7 (0.2-157.2). A radiography technologist received a maximum dose of 157.21. Nurses received the highest average annual effective dose (15.2 +/- 19.46) (0.32-65.58), followed by radiography technologists (14.7 +/- 18.03) (0.4-157.2), and nuclear medicine physicians demonstrated the least dose (8.6 +/- 10.5) (1.2-24.4). The results show that the extremity dose is well below the annual dose limit of 500 mSv. However, there is a wide variation in dose among the workers, underlining a need for careful assessment of working conditions to ensure safe practices for all workers.
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    Diagnostic and therapeutic radioisotopes in nuclear medicine: Determination of gamma-ray transmission factors and safety competencies of high-dense and transparent glassy shields
    (DE GRUYTER POLAND SP Z O O, 2022) Erdemir, Rabiye Uslu; Kılıç, Gökhan; Baykal, Duygu Şen; Almisned, Ghada; Issa, Shams A. M.; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete. Gamma-ray transmission factors of newly designed glass shields are determined using a variety of diagnostic, therapeutic, and research radioisotopes, including Ga-67, Co-57, In-111, Tl-201, Tc-99m, Cr-51, I-131, Co-58, Cs-137, Ba-133, and Co-60. A general-purpose Monte Carlo code MCNPX (version 2.7.0) is used to determine the attenuation parameters of different material thicknesses. Next, the findings are compared using a standard concrete shielding material. The results indicate that adding more CdO to the glass composition improves the overall gamma-ray attenuation properties. As a result, among the heavy and transparent glasses developed, the C40 sample containing 40% CdO exhibited the best gamma-ray absorption properties against all radioisotopes. Furthermore, the gamma-ray absorption characteristics of this created high-density glass were shown to be better to those of a standard and heavy concrete sample. It can be concluded that the newly developed CdO-rich and transparent glass sample may be used in medical radiation fields where the radioisotopes examined are used in daily clinical and research applications.