Measurement of 131I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment

Kostkiewicz

et al. 2021

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This paper presents results of measurements of 99mTc activity concentration in air and nuclear medical personnel blood during ventilation–perfusion SPECT lung scans. 99mTc activity measurements were conducted at the Nuclear Medicine Department, John Paul II Hospital, Krakow. Technicians and nurses who perform examinations were equipped with personal aspirators enabling air sampling to determine the radiation exposure at their workplaces. Measurements allowed to evaluate the concentration of 99mTc in 14 air samples and it ranged from 7800 ± 600 to 10,000 ± 1000 Bq m−3 for air samples collected by technicians and from 390 ± 30 to 600 ± 40 Bq m−3 for air samples collected by nurses. In addition 99mTc concentrations in blood of medical personnel were determined in 24 samples. For technicians the maximum 99mTc blood concentration levels reached 920 ± 70 Bq L−1 and 1300 ± 100 Bq L−1. In the case of nurses, the maximum estimated activity concentrations were about ten times lower, namely 71 ± 7 Bq L−1 and 39 ± 3 Bq L−1. Although the intakes appear to be relatively high, the resulting annual effective doses are about 34 µSv for technicians and only 2 µSv for nurses.

Section: Methodsmentioning

confidence: 99%

99mTc internal contaminations measurements among nuclear medicine medical personnel during ventilation – perfusion SPECT lung scans

Borkowska

Kostkiewicz

et al. 2021

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“…The matrix density was 1.00 g cm −2 . Such method has already been successfully applied for measurements of aerosol and gas activities over the past years (Mietelski et al 2005, 2014; Masson et al 2011; Brudecki et al 2018a).…”

Section: Methodsmentioning

confidence: 99%

“…Finally, doses were calculated based on the time-integrated 99m Tc activity (model of technetium biokinetics and computer simulations), radiation-weighted coefficients (SECALL program, Oak Ridge National Laboratory, Oak Ridge, TN, USA) and tissue-weighting factors according to the ICRP methodology (ICRP 2007). More details on the applied methodology of absorbed dose calculations are given in Li et al (2008) and Brudecki et al (2014, 2017a, b, 2018a, b).…”

Section: Methodsmentioning

confidence: 99%

99mTc activity concentrations in room air and resulting internal contamination of medical personnel during ventilation–perfusion lung scans

Borkowska

Gorzkiewicz

et al. 2019

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This paper presents the results of measurements of 99m Tc activity concentrations in indoor air in a nuclear medicine department and resulting estimated 99m Tc intake by medical personnel. 99m Tc air activity measurements were conducted at the Nuclear Medicine Department, John Paul II Hospital, Krakow, Poland, during ventilation–perfusion SPECT lung scans. Technetium from the air was collected by means of a mobile aerosol sampler with a Petryanov filter operating at an average flow rate of 10 dm 3 min −1 . Measured activities ranged from 99 ± 11 to 6.1 ± 0.5 kBq m −3 . The resulting daily average intake of 99m Tc by medical staff was estimated to be 5.4 kBq, 4.4 kBq, 3.0 kBq and 2.5 kBq, respectively, for male technicians, female technicians, male nurses and female nurses. Corresponding annual effective doses were 1.6 µSv for technicians and 1 µSv for nurses. The highest equivalent dose values were determined for extrathoracic (ET) airways: 5 µSv and 10 µSv for nurses and technicians, respectively. It is concluded that estimated annual absorbed doses are over three orders of magnitude lower than the dose limit established in the Polish Atomic Law Act and in recommendations of the International Commission on Radiological Protection for medical staff.

“…For computer modeling, the SAAM II software from Epsilon Group was used (Barrett et al 1998 ). The method used to calculate radiation doses was presented in detail in previous papers (Li 2018 ; Brudecki et al 2014 , 2017a , b , 2018a , b , 2019 ).…”

Section: Methodsmentioning

confidence: 99%

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

Kluczewska-Gałka

Zagrodzki

et al. 2020

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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.