Proposed Dose Constraints in the Duties of Radiation Workers at the Department of Nuclear Medicine

Chung, Woon-Kwan; Yang, Nam-Hee; Dong, Ke; Choi, Jiho

doi:10.1093/rpd/ncz249

Cited by 3 publications

(2 citation statements)

References 4 publications

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“…Moreover, the doses they receive may easily exceed those of either DR or Gamma Camera technologists. 6 , 7 When dispensing or injecting radiopharmaceuticals, the technologists are close to the radionuclides themselves. As a result, they are exposed to higher levels of radiation, with past International Atomic Energy Agency reports indicating a high, whole-body dose of 8 mSv/year.…”

Section: Discussionmentioning

confidence: 99%

Exposure Doses to Technologists Working in 7 PET/CT Departments

Wei-Guo

Fang

2020

Dose-Response

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Objective: The aim of this study was to measure occupational exposure doses of technologists who dispense and inject radiopharmaceuticals in 7 positron emission tomography/computed tomography (PET/CT) departments. This was done with the goal to help improving protective designs in PET departments and/or establishing national protection standards. Method: Common LiF thermoluminescence dosimeters (TLDs) were placed on the chest and necklace of the technologists to monitor whole-body and thyroid doses, respectively. Ring TLDs were also worn on both index fingers to measure individual hand doses. All TLDs were assembled and measured once every 3 months for a total of 12 months. Additionally, we measured and compared the dose of TLDs attached to both the inside and the outside of the technologist’s lead coat. Results: Technologists received relatively high exposures, which accounted for 64% to 94% of the collective dose in their respective departments. Their thyroid doses ranged from 1.2 to 1.7 mSv/a; some technologists’ hand doses exceeded 500 mSv/a. Use of a lead coat reduced the average dose by 8%. Conclusion: Technologists working in PET/CT departments were the main population exposed to radiation. This work underscores the need for enhanced protective measures for these workers to better reduce their exposure, particularly for their hands.

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Section: Discussionmentioning

confidence: 99%

Exposure Doses to Technologists Working in 7 PET/CT Departments

Wei-Guo

Fang

2020

Dose-Response

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“…The radionuclides inside the bottle can potentially result in unjustified radiation exposure to individuals and the environment. 8,9 Quantification of the radiation levels in the waste is required to ensure the radiological safety of workers and the environment. In normal productions, disposal of activity is recommended after the completion of 10 halflives for the safety of workers and the environment.…”

Section: Introductionmentioning

confidence: 99%

Disposal of Radioactive Waste Generated at the End of 18F- Fluorodeoxyglucose Production for Positron Emission Tomography - Computed Tomography (PET-CT) Scan at Armed Forces Institute of Radiology and Imaging, Rawalpindi

Bilal

Mehdi²,

Slehria³

et al. 2022

PAFMJ

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Objective: To find out the optimal timeline for the safe disposal of radioactive wastes generated at the end of normal and anomalous productions of 18F-Fluorodeoxyglucose for positron emission tomography-computed tomography scans. Study Design: Quasi-experimental study. Place and Duration of Study: Armed Forces Institute of Radiology and Imaging, Rawalpindi Pakistan, from Aug to Dec 2020. Methodology: Wastes generated at the end of 18F-Fluorodeoxyglucose production were tested for residual radioactivity at 2, 12 and 24 hours after synthesis to ascertain the optimal timeline for discarding. The radiation dose at 5 cm from the surface of the container was also assessed. Results: Fifty productions were included in the study, of which 46(92%) were normal, and 4(8%) were anomalous productions. The mean activity at 2 and 24 hours after the end of synthesis was 4.102±0.831mCi and 0.0047±0.00116mCi, respectively, in normal productions and 45.125±2.332mCi and 0.005±0.00026mCi respectively in anomalous productions. The mean radiation dose at 5cm from the surface of the container at 2 and 24 hours after the end of synthesis was 8.2107±1.665mSv/h and 0.00000966±0.00000212mSv/h in normal productions and 90.32±4.66mSv/h and 0.00975±0.0005-mSv/h respectively in anomalous productions. Conclusion: The residual radioactivity in wastes was negligible 24 hours after the end of synthesis in both normal and anomalous productions. Radioactive wastes from 18F-Fluorodeoxyglucose production should, therefore, be conserved for at least 24 hours before their disposal to the environment.

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