Average Annual Effective Dose Research Articles

Analysis of data on levels of public exposure to natural sources of radiation in the Ivanovo region

The paper presents the results of analysis of the Ivanovo Regional databank of radiation doses to the pub-lic from exposure to natural and technologically enhanced radiation background for 2008–2022. Despite the fact that the average individual annual effective dose of public exposure due to natural sources of radiation in the Ivanovo region calculated for the whole 15-year period (4.63 mSv/year) does not qualify as increased (i.e. does not exceed the level of 5 mSv/year), in some years of the period under review the average dose repeatedly exceeded this level, reaching 7.50 mSv/year. The analysis of the structure of the doses of public exposure due to natural sources of radiation in the Ivanovo region showed that the contribution of the dose from internal exposure to radon, thoron and progenies according to measurement results from 2008–2022 ranged from 65.98 to 81.47%. The paper provides examples of buildings of different types in settlements of the Ivanovo region, in which the indoor radon isotopes equilibrium equivalent concentrations are more than 1.5 times higher than the established action level for existing dwellings and public buildings (200 Bq/m3). Despite the significant amount of measurement data in the Regional databank, it is necessary to obtain additional information on the indoor radon levels in existing wooden and other low-rise dwellings and public buildings in the most radon-prone areas of the region. For this purpose, a radon survey is planned for 2024-2026 in the cities of Ivanovo and Kohma, Privolzhsky, Gavrilovo-Posadsky, Teykovsky and Zavolzhsky districts of the Ivanovo region within the framework of a joint project of Saint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, the Directorate of the Federal Service for Surveillance on Consumer Rights Protection and Human Wellbeing in the Ivanovo region, and the Center of Hygiene and Epidemiology in the Ivanovo region.

Po-210 in plankton and fish from coastal waters (gulf of Trieste, northern Adriatic Sea)

The activity concentrations of Po-210 were determined in seawater (<0.45 μm), suspended particulate matter (0.45–20 μm), fractionated plankton (20–50 μm, 50–200 μm, >200 μm) and tissues from four fish species, namely European seabass (Dicentrarchus labrax), Golden grey mullet (Chelon auratus), Gilt-head bream (Sparus aurata) and Common pandora (Pagellus erythrinus), collected in the Gulf of Trieste (northern Adriatic Sea). The activity concentration of Po-210 in seawater varied from 0.4 to 2.2 mBq/L in the dissolved phase (<0.45 μm) and from 0.4 to 0.8 Bq/L in suspended particulate matter (0.45–20 μm). Plankton fractionation showed the levels of 62–395 Bq/kg Po-210 in the >200 μm mesoplankton fraction, 65–459 Bq/kg in 50–200 μm and 52–537 Bq/kg in 20–50 μm microplankton fractions. No significant differences were found between fractions. The Po-210 distribution trend in fish tissues was in order: liver > stomach with intestine > kidney > spleen > gonads > gills > muscle. Bioaccumulation factors were determined for fish tissues indicating that the amount of Po-210 mostly depends on fish feeding habits. Hence, the main pathway entry of Po-210 is through ingested food. The highest estimated average total annual effective ingestion doses of Po-210 are obtained via the consumption of Common Pandora (7.1 μSv/year to 16.5 μSv/year) while the lowest doses are due to the consumption of European seabass (0.32 μSv/year to 0.76 μSv/year). Comparison with levels reported for other Mediterranean and Atlantic areas showed that only activitiy concentrations of Po-210 in fish appear significantly different, most likely because different fish species were analysed. The human dose exposure via fish consumption in the area is rather low.

Measurement of Background Ionizing Radiation Around Beta Glass Plc and Its Environs, Ughelli, Delta State, Nigeria

A study of the background ionizing radiation levels to helps monitor the impact of human activities on the environment, such as mining, farming, glass bottle production and power generation has been carried out around Beta glass Plc and Transcorp Power LTD using a hand-held gamma spectrometer (GAMMA-SCOUT; Geiger counter Radiation meter) and GPS (Oregon-450 Garmin). The study of the BIR levels was carried out between June to July, 2022. The average measured exposure rates (AV. BIR) ranged from 0.007 mRh-1 to 0.013 mRh-1, with 0.010±0.0002 mRh-1 as the average. The estimated mean outdoor absorbed dose rate (ADR) for the study region was 113.10 Gyh-1 to 87.153±2.091 Gyh-1, with an average annual effective dose equivalent (AEDE) of 106.884±2.565 mSvy-1 and an average excess lifetime cancer risk (ELCR) of (0.374±0.009) × 10-3. The measured values of radiological parameters, such as annual dose rate, annual effective dose rate, and excess lifetime cancer, were higher than background radiation levels. The average BIR is in line with the ICRP recommendation of 0.013 (mRh-1), while the effective dose rate (EDR) is somewhat below the ICRP recommendation of 1.00 (mSvy-1) for a normal environment. The obtained values of the radiological indicators, such as ADR, AEDE, and ELCR, are greater than the background radiation norm of 59 (?Gyh-1), 0. 07 (mSvy-1), and 0.29×10-3. The study found that radiation levels and doses in the study location do not immediately harm personnel or residents, but increased lifetime cancer risk values suggest that cumulative dosages may cause cancer.

Assessment of radiation exposure in the phosphate mining area of Gafsa (Southeastern Tunisia)

ABSTRACT This study investigates the radiological health implications of sixty-three (63) samples of soil, food, and drinking water collected from the phosphate mining area of Gafsa in Southeastern Tunisia. Additionally, it assesses the exposure to radon concentrations in houses located around the phosphate mining sites. The activity concentrations in soil samples were found to be 382.1, 36.1 and 16.3 Bq kg−1 respectively for 40K, 232Th and 226Ra. The average activity of 232Th was higher than worldwide average value of 30 Bq kg−1. Eleven (11) radiological hazard parameters were computed based on various exposure scenarios including external gamma dose rate (GDR), annual effective dose (AED) and risk assessment (RA). The calculated GDR values were of 3.2 nGy h−1 in food and 45.4 nGy h−1 in soil samples, while the average AED values were of 3.9 µSv y−1 in food and 83.5 µSv y−1 in soil samples. Internal AED due to ingestion of radionuclides was found to have a mean value of 0.1 µSv y−1 in soil, 264.4 µSv y−1 in food and 10 µSv y−1 in drinking water samples. The AED values due to inhalation of soil-dust and radon were assessed to be 2.1 and 1.2 µSv y−1, respectively. The RA average values in food and drinking water samples were found to be 3 × 10−5 and 2.4 × 10−4, respectively. Based on the exposure pathway, inhalation of radioactivity through soil and radon resulted in highest total AED values, which remained below the reference limit. This was followed by internal exposure, with total AED values of 274.5 µSv y−1.

Examining the Radiological Health Risks Associated with Water Sourced from the Ogwashi-Uku Earth Dam in Ogwashi-Uku, Delta State, Nigeria

Given the increased human activities and population growth in Ogwashi-Uku, there is a possibility of potential contamination of the water in the dam with elevated levels of alpha and beta radiation. Therefore, this study aimed to assess the radiological health risks associated with water obtained from the Ogwashi-Uku Earth dam by analyzing the concentrations of gross alpha and gross beta activity in the water. The results indicate that the measured activity concentrations of gross alpha and gross beta in the water samples are below the permissible limits of 0.1 Bq/l and 1.0 Bq/l respectively. Additionally, the average annual effective dose equivalent calculated for all the water samples is lower than the recommended dose limit of 0.1 mSv for radionuclides in water. These findings suggest that the assessed life cancer risk associated with the water consumption is low, indicating that the water from the Ogwashi-Uku Earth dam is safe for consumption.

Determination of Activity Concentration and Radiological Risks from Gold Mine Tailings around Ilahun-Ijesa in Obokun Local Government, Osun State, Nigeria

In this study, the activity concentrations and radiological risks associated with exposure to NORMS in soils around the gold mine tailings in Ilahun – Ijesa, Obokun Local Government, Osun State, Nigeria was evaluated. A Sodium Iodide (NaI) gamma spectroscopy was used to determine the activity concentrations of the natural radio nuclides in soil samples that were collected from the gold mine tailings. The mean activity concentration for 238 U, 232 Th and 40K were 14.50±2.40, 10.45±3.20 and 332.70±6.10 Bqkg-1 respectively. The average absorbed dose was calculated to be 26.4 nGy/h and the corresponding average annual effective dose was found to be 0.0031 mSv, which is less than the total annual effective dose of 1 mSv recommended by ICRP for public exposure control. Radiological hazard parameters were evaluated from activity concentrations and the average values were found to be lower than recommended safety limits.

Assessment of radon levels in some cosmetics using CR-39 nuclear detector

People across the globe use cosmetics, thus studying radon in makeup is crucial for finding solutions to lessen its harmful impacts. The research is concerned with examining the amounts of radon and annual dose in cosmetics sold in Saudi Arabian marketplaces. The radioactive content of cosmetics was measured using the CR-39 detector. The results showed that the radon concentration values were within the internationally permissible limit, which ranges between 200 and 600 Bq/m3. The average value of radon concentration for all measured cosmetics was 237.94 Bq/m3. The results of the annual effective dose showed that 75% of the values were within the safe range. The average annual effective dose of radon was 4.11 mSv/year. Ads and Mineral products recorded values above the globally permitted values for all measured parameters. It is advised to stay away from high-value cosmetics. Using cosmetics with high radiation content can be harmful to the general public's health. It is advised to keep learning about makeup styles from around the globe.

Estimation of effective doses to whole-bodies and hands of facilitating staff from radioiodine-131 ablation therapy patients

BackgroundWorkers in the field of radiation therapy are exposed to radiation hazards, and it is necessary to take precautions to limit the radiation dose to nursing staff and physicists.ObjectiveTo evaluate the external dose rate (EDR), effective whole-body dose (EHD) and hand equivalent dose (HED) for facilitating staff from radioiodine-131 (RAI-131) ablation therapy patients.MethodsOne hundred and eighty patients were selected from two radiotherapy centers in Cairo, Egypt in this study and divided into three groups, Group-A, Group-B and Group-C according to administered activities of (RAI-131) of 3700 MBq, 4440 MBq and 5550 MBq for ablation therapy patients respectively. The EDR, EHD and HED were measured using electronic dosimeters.ResultsThe average EDR were 79.1 ± 12.1, 22.7 ± 8.5, 7.0 ± 4.0, 2.9 ± 1.3 and 1.9 ± .9.0 μSv h−1 for group-A, and about 87.8 ± 14.0, 25.6 ± 9.0, 8.1 ± 5.0, 3.4 ± 2.0 and 2.4 ± 1.0 μSv h−1 for group-B and were 93.5 ± 17.0, 31.6 ± 11.0, 10.1 ± 7.0, 4.7 ± 3.0 and 3.4 ± 1.5 μSv h−1 for group-C at 2 h, second, third, fourth and fifth days, respectively after administration of RAI-131. The average annual effective doses were 2.76 ± 0.09 and 1.55 ± 0.05 mSv at center 1, and were about 2.96 ± 0.09 and 1.71 ± 0.06 mSv at center 2 for physicists and nurses, respectively.ConclusionThe EDR as well as the EHD and the HED received by radiation therapy workers up to the fifth day of administered activity RAI-131 were within the limits of values recommended by the International Commission on Radiation Protection (ICRP).

Trends of occupational exposure to ionizing radiation in Central China for the period 2000–2021

A retrospective analysis of occupational exposure to ionizing radiation from medical uses and industrial uses in the three provinces of Central China from 2000 to 2021 was conducted. The average annual effective dose in medical uses and industrial uses decreased from 2.042 mSv and 2.334 mSv in 2000–2002 to 0.476 mSv and 0.371 mSv in 2021 respectively; the fraction of monitored workers receiving annual dose not exceeding 1 mSv increased from 60.78% and 74.45% in 2000–2002 to 94.20% and 96.85% in 2021 respectively, while receiving annual doses exceeding 20 mSv declined from 1.35% and 1.91% in 2000–2002 to 0.18% and 0.03% in 2021 respectively. The average annual effective dose and NR20 in the period 2000–2021 were relatively high in professional public health institutions (0.955 mSv and 0.004) and hospitals (0.815 mSv and 0.004). In 2021, the average annual effective dose to monitored workers in different occupational categories in medical uses in the three provinces of Central China were in the range of 0.199–0.692 mSv, with interventional radiology received the highest dose and NR20 (0.692 mSv and 0.005); the average annual effective dose ranged from 0.161 to 0.493 mSv in industrial uses, with industrial radiography received the highest dose and NR20 (0.493 mSv and 0.001). Occupational exposure in medical uses and industrial uses declined obviously in Central China, and the groups receiving higher doses are the radiation workers working in hospitals and professional public health institutions, or engaged in interventional radiology, nuclear medicine and industrial radiography, warranting more effective radiation protection measures.

Health Effects Associated with Occupational Exposure to Gamma Radiation in Aircrew: A Case Study on Mehrabad Airport in 2021

Introduction: Aircrew is exposed to harmful levels of gamma radiation with unknown effects. This study aims to investigate occupational exposure to cosmic gamma radiation and its associated health effects among the aircrew members of Iran Airlines.&#x0D; Methods: This analytical cross-sectional study was carried out on the crew from four internal flights departing from Mehrabad Airport in 2021. The participants were divided into two groups of 100 aircrew members flying on low-altitude and high-altitude routes, and the history of their illnesses in the past thres years was extracted from medical records. The average annual effective dose (ED) of gamma radiation for the aircrew was measured by dosimeter (CEM DT-9501), and data analysis was done using SPSS16 software.&#x0D; Results: This study found that the average annual ED of gamma rays was approximately 1.5 millisieverts higher in flight crews on high-altitude flights compared to the low-altitude ones. Moreover, a significant relationship was observed between exposure to gamma and occupational disease in the studied subjects (P &lt; 0.05). Therefore, the risk of gastrointestinal, skin, and cardiovascular diseases was 3.55, 3.63, and 12.4 times higher for the crew on high-altitude flights compared with those on low-altitude flights.&#x0D; Conclusion: High-altitude flights are associated with increased exposure to gamma radiation, leading to a threefold higher risk of occupational diseases such as gastrointestinal, skin, and cardiovascular conditions among aircrew members. These findings highlight the importance of reducing health risks of exposure to gamma rays in aviation industry and emphasize the need for preventive measures to protect the well-being of aircrew personnel.

ASSESSMENT OF RADIATION RISK LEVELS ASSOCIATED WITH NATURAL (226RA, 232TH, AND 40K) AND ARTIFICIAL (137CS) RADIONUCLIDES PRESENT IN POWDERED MILK SOLD AND CONSUMED IN SENEGAL

The study conducted in Senegal sought to address the dearth of data on radionuclide concentrations in milk, particularly considering the upward trajectory of domestic consumption. Employing gamma-spectrometry, researchers investigated five milk brands, calculating the resulting ingestion dose. The concentrations of 232Th, 226Ra, 137Cs, and 40K exhibited variability across brands, ranging from 0.40 ± 0.30 for G1 to 7.58 ± 0.37 for V1, 0.50 ± 0.17 for V1 to 1.15 ± 0.11 for D1, 0.06 ± 0.05 for V1 to 0.43 ± 0.06 for D1, L1, G1, and H1, and 16.31 ± 4.02 for L1 to 369.26 ± 15.84 Bq/kg for G1. Notably, the total average Annual Effective Dose for all age groups remained consistent across all brands. Importantly, the concentrations observed were found to be significantly below the guidance level recommended by the World Health Organization (WHO). As a result, the study concludes that all five milk brands investigated are considered safe for consumption, providing reassurance to the public regarding the radionuclide content in the milk supply chain in Senegal.

Radiological landscape of natural resources and mining: Unveiling the environmental impact of naturally occurring radioactive materials in Ghana's mining areas

This study provides a general observation of the status of naturally occurring radioactive materials (NORMs) distribution in mining and industrial areas of Ghana in order to establish regional and national data on NORMs. The study includes data on radioactivity concentrations of U-238, Th-232, and K-40 in soils and for water concentrations of Ra-226, Th-228, and K-40 from various mining, oil, and gas communities, as well as water sources used for crop farming and farmlands. The average activity concentrations of U-238, Th-232, and K-40 in the soil samples were found to be 59 ± 16 Bq/kg, 48 ± 15 Bq/kg, and 286 ± 57 Bq/kg, respectively. The average concentration of Ra-226, Th-228, and K-40 in the water samples were found to be 1.62 ± 0.33 Bq/L, 2.08 ± 0.53 Bq/L, and 22.36 ± 3.44 Bq/L, respectively. The estimated average annual effective doses from external and internal exposure pathways in soil and water samples were 0.09 mSv/y and 0.54 mSv/y, respectively. The total annual effective dose resulting from both exposure pathways was calculated to be 0.63 mSv/y, which is below the 1 mSv/y dose limit recommended by the International Commission on Radiological Protection (ICRP) for controlling public radiation exposure. Based on the radiological hazard indices, the majority of the soil samples were found to be suitable as building materials as their respective indices were below the limits except for two sample locations and the sludge and scale samples. The average Excess Lifetime Cancer Risk (ELCR) value of the water samples was 1.6 times greater than the recommended value of 1.16 × 10−3, presenting a relatively higher risk to the public of developing cancer. No significant regional differences in the levels of radioactive elements. The regression models demonstrate strong interrelationships between the studied elements, with high R-squared values suggesting a predictable nature of one element’s concentration based on others.

Результаты контроля радона в жилых домах вблизи разработки Шкурлатовского месторождения гранита

The presence of acting granite quarrying near the residential area may cause increase in indoor radon concentration. The paper presents results of estimating the level of radiation and carcinogenic danger for residents living near the acting Shkurlatov granite deposit. To assess average annual equivalent equilibrium volume activity (EEVA), Bq/m3, and the average annual individual effective radiation doses from radon isotopes presented in the indoor air, mSv/year, the data of the unified system for individual doses monitoring from 2017 through 2022 were used. Results of voluntary in-situ examination and 42 measures of radon volume activity in 17 residential buildings the closest to the granite quarry, were carried out in 2023. The above measures were used for calculation of EEVA of radon isotopes (Bq/m3) and the average annual individual effective radiation dose to the residents inhalated indoor radon (mSv/year). According to the data on radon monitoring in the dwellings situated near the Shkurlatov granite deposit the EEVA in wooden houses varied from 9.2 to 35.5 Bq/m3, EEVA in stone houses varied from 9.4 to 41.4 Bq/m3, average values are 21.22.0 and 21.91.8. The quoted values do not differ from the monitoring data in the Pavlovsk district of the Voronezh Region. Statistic data on malignant neoplasms incidence from 2017 through 2022 were investigated. As for the incidence of trachea, bronchus and lung cancer, no statistically significant difference between average multiyear cancer incidence in the area close to the Shkurlatov granite deposit in Pavlovsk district, Voronezh region, and in the more favorable district. The comparison was based on annual radiation doses due to radon isotopes inhalation. The results of the study suggest that radon at the registered indoor concentration does not affect cancer incidence among people living near the Shkurlatov granite deposit.

Evaluating internal exposure due to intake of 131I at a nuclear medicine centre of Dhaka using bioassay methods

Handling of radioisotopes may cause external and internal contamination to occupational workers while using radiation for medical purposes. This research aims to monitor the internal hazard of occupational workers who handle 131I. Two methods are used: in vivo or direct method and in vitro or indirect method. The in vivo or direct method was performed by assessing thyroid intake with a thyroid uptake monitoring machine. The in vitro or indirect method was performed by assessing urine samples with the help of a gamma-ray spectroscopy practice using a High-Purity Germanium (HPGe) Detector. In this study, fifty-nine thyroid counts and fifty-nine urine samples were collected from seven occupational workers who were in charge of 131I at the National Institute of Nuclear Medicine and Allied Sciences (NINMAS), Dhaka. The result showed that the average annual effective dose of seven workforces from thyroid counts were 0.0208 mSv/y, 0.0180 mSv/y, 0.0135 mSv/y, 0.0169 m Sv/y, 0.0072 mSv/y, 0.0181 mSv/y, 0.0164 mSv/y and in urine samples 0.0832 mSv/y, 0.0770 mSv/y, 0.0732 mSv/y, 0.0693 mSv/y, 0.0715 mSv/y, 0.0662 mSv/y, 0.0708 mSv/y.The total annual effective dose (in vivo and in vitro method) was found among seven workers in average 0.1039 mSv/y, 0.0950 mSv/y, 0.0868 mSv/y, 0.0862 mSv/y, 0.0787 mSv/y, 0.0843 mSv/y, 0.0872 mSv/y. Following the rules of the International Commission on Radiological Protection (ICRP), the annual limit of effective dose for occupational exposure is 20 mSv per year and the finding values from this research work are lesser than this safety boundary.

Examining External Dose Rates in Mamuju Regency, Indonesia: A Personal Radiation Dosimetry Approach

This study aimed to quantify the individual external radiation exposure in Mamuju, Indonesia. A SmartRad portable personal dosimeter was utilized for this purpose, and data was collected over a period of 30 days. The findings indicate that the dose rate varies from 0.152 to 4.200 μSv/h and cumulatively ranges from 0.1 to 8.4 μSv/day based on an average measurement duration of 160 minutes. The average dose rate in areas with mineral deposits is 11.02 mSv per year. In contrast, the average effective dose in areas without radioactive mineral deposits is 2.6493 mSv per year. The annual average effective dose for individuals was measured at 6.8347 mSv. These findings imply that personal exposure to radiation among the public in Mamuju exceeds the threshold recommended by the International Commission of Radiological Protection.

Analysis of radon concentrations in drinking water in coastal regions of Karnataka, South India.

The measurements of radon activity in water samples from several parts of Karnataka were studied. Drinking water quality is a routine tool in health and environmental research. Radon exposure puts the entire public at risk for radiological damage through inhalation and ingestion. Radon concentrations were measured using the emanometry technique. Estimated 222Rn activity concentration in water has been found to vary from 2.05 to 28.02Bql-1 with an average value of 7.38Bql-1. For all samples under study, the total average annual effective doses are much less than the safe limit of 100μSv y-1.

Estimation of natural radioactivity in the soil samples around the uranium site, royal village, Khandela, Sikar district, Rajasthan.

The measurements of activity concentration of radium ( 226Ra ), thorium ( 232Th) and potassium ( 40K ) natural radionuclides using high purity germanium ( HPGe ) detector to assess harmful effects on people residing around Royal Uranium Site, Sikar, Rajasthan, India. The activity concentrations range from 29.03±3.72 to 69.95±4.07Bq/kg for 226Ra with a mean value of 47.01Bq/kg, 57.99±6.13 to 113.94±6.54Bq/kg with a mean value of 86.56Bq/kg for 232Th,678.19±76.36 to 1426.55±81.32Bq/kg for 40K with a mean value of 1195Bq/kg. Average Radium Equivalent Activity was measured 261.59±35.48Bq/kg. The total outdoor absorbed gamma dose rate ranged from 78.42 to 157.91 nGy/h with a mean value of 122.12 nGy/h.The average annual effective dose equivalent outdoors and indoors was found 0.75mSv.Mean external (Hex) and internal (Hin) hazard indices are measured 0.70 and 0.82, respectively, for the study area.

Comparison of effective doses for personnel performing flaw detection in stationary conditions and &lt;i&gt;in situ&lt;/i&gt;

Official data on radiation doses for flaw detectors do not take into account working conditions. In the reporting forms, there is no division between personnel performing flaw detection in stationary conditions and in situ, which roughly averages the values of effective doses towards underestimating the values for personnel working in site radiography. In this work, comparison of our own data on radiation doses of flaw detectors was performed. It has been shown that the difference in the mean and median values of effective doses reaches 10 times. When performing flaw detection in stationary conditions, the personnel are at a sufficient distance from the source of ionizing radiation and are well shielded by engineering protective equipment, so the exposure is fairly uniform. In such cases, one individual thermoluminescent dosimeter located at chest level is sufficient to estimate the effective dose. The average annual effective dose for personnel conducting flaw detection in stationary conditions is 0.87 mSv (median – 0.88 mSv, maximum value – 0.99 mSv). During individual radiation monitoring of personnel performing flaw detection in situ using portable roentgen flaw detectors, cases of neglect in the use of individual dosimeters were identified, which requires more stringent measures to comply with existing requirements for ensuring radiation safety and operating rules for individual dosimeters. The average annual effective dose for flaw detectors working with portable roentgen flaw detectors is 9.03 mSv (median – 8.85 mSv, maximum value – 12.37 mSv).

Assessment of extremity dose for medical staff involved in positron emission tomography/computed tomography imaging: Retrospective study.

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.

Assessment of the Radiation Situation and the Presence of Heavy Metals in the Soil in the Poleski National Park

The aim of the research in the Poleski National Park was to determine the concentration of radionuclides and heavy metals in the soil and to evaluate the absorbed dose and the average annual effective dose as a result of external exposure to ground-based radiation sources. The spread of anthropogenic radionuclide concentration in the Poleski National Park was the highest. This is a first-of-its-kind study in Poland. The annual effective dose calculated for the Poleski National Park was over three times higher than the average worldwide value. Soil samples were subjected to mineralization using a TITAN MPS with a rotor. Subsequently, the metals in the obtained solutions were determined using the atomic absorption spectrometry method with flame atomization (AAS FM). The content of copper Cu, nickel Ni, lead Pb, cadmium Cd, and chromium Cr did exceed the average content neither in Europe nor around the world. The soils of the Poleski National Park are characterized by pollution with the tested heavy metals, especially cadmium Cd.