Time-related study on external exposure dose of 2-deoxy-2-[F-18]fluoro-d-glucose PET for workers’ safety

Takahashi, Yasuyuki; Hosokawa, Shota; Tsujiguchi, Takakiyo; Monzen, Satoru; Kanzaki, Takao; Shirakawa, Koji; Nemoto, Ayaka; Ishimura, Hayato; Oriuchi, Noboru

doi:10.1007/s12194-019-00548-0

Cited by 3 publications

(1 citation statement)

References 10 publications

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“…Occupational exposure in PET cyclotron facilities differ from regular nuclear medicine departments because of the 511 kev gamma photons and also the secondary neutron emission during bombardment [9][10][11]. This fact mandates the establishment of good radiation safety practices and a robust radiation protection program.…”

Section: Comparison Of Dose Estimates With Other Studiesmentioning

confidence: 99%

Commissioning of the first hospital-based PET radiopharmaceutical cyclotron in Greece: personnel dose assessment

Ioannidou,

Katsouli,

Doika

2024

J. Radiol. Prot.

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The role of positron emission tomography (PET) imaging with 2-fluoro-2-deoxy-D-glucose (FDG) is well established in the diagnosis and management of cancer patients. As the demand for PET imaging continues to rise, many hospitals are installing on-site self-shielded mini cyclotrons to produce their own radiopharmaceuticals, including FDG. In May 2021, the Dose-on-Demand Biomarker Generator (BG-75) was installed at the Metaxa Cancer Hospital in Greece, making it the first hospital-based PET radiopharmaceutical cyclotron in the country. During commissioning, the expected external exposure for personnel was established, and internal exposure was found to be negligible. Personnel dose was estimated with two methods: survey meter measurements in various locations combined with the time spent in each location, and direct measurement using electronic personal dosemeters. Gamma and neutron radiation readings outside the cyclotron vault were at background levels. Inside the cyclotron vault, the highest recorded readings by the target were 18 μSv/h for both gammas and neutrons; at one meter, the values were 5 μSv/h and 4 μSv/h, respectively. Based on these measurements, the annual expected whole-body dose per operator is 0.6 mSv, and the respective extremity dose is 16 mSv. The annual expected whole body and extremity dose for the radiochemist is 0.3 mSv and 25 mSv, respectively. The expected dose estimates for the medical physicists are also below 1 mSv. These doses are well below the regulatory limits and local As Low As Reasonably Achievable (ALARA) levels. With experience and a robust ALARA program, personnel exposure could be further reduced.

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Section: Comparison Of Dose Estimates With Other Studiesmentioning

confidence: 99%

Commissioning of the first hospital-based PET radiopharmaceutical cyclotron in Greece: personnel dose assessment

Ioannidou,

Katsouli,

Doika

2024

J. Radiol. Prot.

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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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Evaluation of Lens Doses among Medical Staff Involved in Nuclear Medicine: Current Eye Radiation Exposure among Nuclear-Medicine Staff

et al. 2023

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The International Commission on Radiological Protection has lowered the annual equivalent eye-lens dose to 20 mSv. Although occupational exposure can be high in nuclear medicine (NM) departments, few studies have been conducted regarding eye-lens exposure among NM staff. This study aimed to estimate the annual lens doses of staff in an NM department and identify factors contributing to lens exposure. Four nurses and six radiographers performing positron emission tomography (PET) examinations and four radiographers performing radioisotope (RI) examinations (excluding PET) were recruited for this study. A lens dosimeter was attached near the left eye to measure the 3-mm-dose equivalent; a personal dosimeter was attached to the left side of the neck to measure the 1-cm- and 70-µm-dose equivalents. Measurements were acquired over six months, and the cumulative lens dose was doubled to derive the annual dose. Correlations between the lens and personal-dosimeter doses, between the lens dose and the numbers of procedures, and between the lens dose and the amounts of PET drugs (radiopharmaceuticals) injected were examined. Wilcoxon’s signed-rank test was used to compare lens and personal-dosimeter doses. The estimated annual doses were 0.93 ± 0.13 mSv for PET nurses, 0.71 ± 0.41 mSv for PET radiographers, and 1.10 ± 0.53 mSv for RI radiographers. For PET nurses, but not for PET or RI radiographers, there was a positive correlation between the numbers of procedures and lens doses and between amounts injected and lens doses. There was a significant difference between the lens and personal-dosimeter doses of PET nurses. The use of protective measures, such as shielding, should prevent NM staff from receiving lens doses > 20 mSv/year. However, depending on the height of the protective shield, PET nurses may be unable to assess the lens dose accurately using personal dosimeters.

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Time-related study on external exposure dose of 2-deoxy-2-[F-18]fluoro-d-glucose PET for workers’ safety

Cited by 3 publications

References 10 publications

Commissioning of the first hospital-based PET radiopharmaceutical cyclotron in Greece: personnel dose assessment

Commissioning of the first hospital-based PET radiopharmaceutical cyclotron in Greece: personnel dose assessment

Exposure Doses to Technologists Working in 7 PET/CT Departments

Evaluation of Lens Doses among Medical Staff Involved in Nuclear Medicine: Current Eye Radiation Exposure among Nuclear-Medicine Staff

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