Variation of counting efficiency in determination of 131I activity in the thyroid gland as a result of its position relative to the detector

Kierepko, Renata; Janowski, Paweł; Grochowska, M.

doi:10.1007/s10967-014-3051-z

Cited by 6 publications

(6 citation statements)

References 5 publications

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“…The total mass of the shielding is 18 t. The spectrometer consists of two germanium detectors manufactured by Ortec, each characterised by a relative efficiency of 30% (Mietelski et al 2013 ). Performance calibration was carried out with an adult thyroid phantom including a sodium iodide solution with an activity of ca 6 kBq (Kierepko et al 2014 ). A phantom thyroid lobe with dimensions of 5.5 cm in length, 2.5 cm in width and 2 cm in height was applied.…”

Section: Methodsmentioning

confidence: 99%

Measurement of 131I activity in thyroid of nuclear medical staff and internal dose assessment in a Polish nuclear medical hospital

Brudecki

Kowalska

Zagrodzki

et al. 2016

Radiat Environ Biophys

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This paper presents results of 131I thyroid activity measurements in 30 members of the nuclear medicine personnel of the Department of Endocrinology and Nuclear Medicine Holy Cross Cancer Centre in Kielce, Poland. A whole-body spectrometer equipped with two semiconductor gamma radiation detectors served as the basic research instrument. In ten out of 30 examined staff members, the determined 131I activity was found to be above the detection limit (DL = 5 Bq of 131I in the thyroid). The measured activities ranged from (5 ± 2) Bq to (217 ± 56) Bq. The highest activities in thyroids were detected for technical and cleaning personnel, whereas the lowest values were recorded for medical doctors. Having measured the activities, an attempt has been made to estimate the corresponding annual effective doses, which were found to range from 0.02 to 0.8 mSv. The highest annual equivalent doses have been found for thyroid, ranging from 0.4 to 15.4 mSv, detected for a cleaner and a technician, respectively. The maximum estimated effective dose corresponds to 32% of the annual background dose in Poland, and to circa 4% of the annual limit for the effective dose due to occupational exposure of 20 mSv per year, which is in compliance with the value recommended by the International Commission on Radiological Protection.

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Section: Methodsmentioning

confidence: 99%

Measurement of 131I activity in thyroid of nuclear medical staff and internal dose assessment in a Polish nuclear medical hospital

Brudecki

Kowalska

Zagrodzki

et al. 2016

Radiat Environ Biophys

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“…Internal radiation monitoring and dose estimation should be carried out for nuclear medicine workers. Internal radiation monitoring is mainly carried out through methods such as air sampling, in vitro direct measurement, biological sample analysis (DNA strand breaks in leukocytes of peripheral blood), and other methods (14)(15)(16)(17)(18)(19). Recommended dose estimation method by ICRP and GBZ 129-2016 and related occupational dose software, with the advent of the use of radioactive sources in various fields such as health physics, industry, energy, and environmental applications, nuclear radiation detectors have become the most fundamental instruments.…”

Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Thyroid dose assessments due to inhalation of 131I for nuclear medicine workers

Liu

Zhang

et al. 2022

Front. Public Health

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BackgroundIn general, medical staff who work in nuclear medicine should be entirely safe in their professional environment. Nevertheless, we already know that the working environment of the nuclear medicine staff is not completely safe due to the handling of high amounts of radionuclides for diagnostic and therapy applications, which is especially relevant for 131I (as a non-sealed source).PurposeThe goal of this study was to assess the inhaled 131I thyroid dose in nuclear medicine workers and to introduce a simple method for internal exposure monitoring.MethodsUsing 2-IN*2-in NaI (Tl) scintillation spectrometer and its supporting software (InSpector Maintenance Utility and Genie 2000), from 2019 to 2021, internal thyroid irradiation monitoring, an internal thyroid irradiation monitoring investi A NaI (Tl) scintillation spectrometer and its sugation was carried out for 3 consecutive years, between 2019 and 2021, in staff members of nuclear medicine departments engaged with iodine therapy.Results131I activity was found highest in the thyroid of nuclear medicine workers involved with the manual packaging and delivery of the radioisotope, while it was not detected in staff members involved with the automatic packaging and drug delivery. The activity range was found to be 30.00 ± 6.60–6070.00 ± 1335.40 Bq for the exposed personnel, and the estimated dose was 0.05–6.77 mSv. In 2021, three workers had an annual equivalent dose above 5 mSv.ConclusionBy monitoring the thyroid 131I in staff members of the nuclear medicine department, it was found that there are 131I internal occupational exposure risks. The best solution is automatic packaging and drug delivery.

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“…The average detector efficiency was estimated to be (0.31 ± 0.08) %. The estimated uncertainty is relatively high, namely 25%, because it takes into account the large uncertainty due to the relative position of the thyroid gland and the detector (Kierepko et al 2014 ). This high uncertainty of the efficiency propagates to a relatively high uncertainty of 131 I activity in the thyroid gland.…”

Section: Methodsmentioning

confidence: 99%

131I thyroid activity and committed dose assessment among family members of patients treated with radioactive iodine

Brudecki

Kluczewska-Gałka

Zagrodzki

et al. 2020

Radiat Environ Biophys

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The main goal of the present study was estimation of an internal contamination of 131 I among family members of patients treated with radioactive iodine. Thyroid activity measurements of 131 I in examined volunteers were performed using a whole-body spectrometer at the institute of nuclear physics, Polish academy of sciences. During this research, 20 relatives of patients treated with 131 I were examined: eight women and 12 men with an age in the range from 3 to 72 years. In the case of nine individuals, the activity of 131 I in the thyroid was below the detection limit, but among the remaining 11 individuals, the activity varied from (9 ± 3) Bq up to (1140 ± 295) Bq. Subsequently, based on the measurements of thyroid 131 I activities, the corresponding doses were assessed. The highest estimated effective dose reached 218 μSv, while the thyroid equivalent dose was 2.4 mSv. In addition, the experimental data obtained were statistically analysed together with the results of surveys of the individuals participating in the study by means of correspondence analysis and nonparametric tests: Mann–Whitney, gamma, χ 2 and Yule Phi coefficient. These analyses revealed relationships between 131 I activities in the thyroids of the examined individuals and their housing conditions as well as consumption of meals prepared by the patients.

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Variation of counting efficiency in determination of 131I activity in the thyroid gland as a result of its position relative to the detector

Cited by 6 publications

References 5 publications

Measurement of 131I activity in thyroid of nuclear medical staff and internal dose assessment in a Polish nuclear medical hospital

Measurement of 131I activity in thyroid of nuclear medical staff and internal dose assessment in a Polish nuclear medical hospital

Thyroid dose assessments due to inhalation of 131I for nuclear medicine workers

131I thyroid activity and committed dose assessment among family members of patients treated with radioactive iodine

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