The activity of 210Pb in cigarette smoked in Kazakhstan.

The radon decay product 210Pb is a known component of tobacco. In this study, the activity concentration of 210Pb in the most popular cigarette brands (six samples) for Kazakhstan consumers was determined by beta spectrometry. The activity levels of 210Pb ranged between 2.69 ± 0.27 and 27.42 ± 2.74 mBq per cigarette. Higher activity concentrations for 210Pb were found in Sample No.4 and showed an excess of the world average by 1.8 times. The average activity concentrations of 210Pb in cigarette tobacco were 10.42 ± 1.04 mBq cig-1. The daily activities inhaled in the lungs of a smoker, and the resulting effective doses due to cigarette smoking were calculated. Effective doses per year due to cigarette smoking were calculated assuming that 42.13% of the 210Pb in tobacco were retained in the lungs of the smokers. It is concluded that for a smoker in Kazakhstan, the average effective dose ranges from 9.1 ± 0.9 µSv/year to 92.8 ± 9.3 µSv/year for a cigarette consumption of one pack of cigarettes per day. The results indicate that the annual effective doses from inhalation of 210Pb due to smoking one pack of cigarettes per day are from 7 to 58 times (for different types of cigarettes) greater than the annual effective doses from ingestion of radionuclides via the diet.

Assessment of internal radiation exposure caused by radon in commercially bottled spring waters consumed in Turkey.

The variation of dissolved radon levels in water supplies remains of interest since radon ingested through drinking water can give considerable radiation to the lining of the stomach. This study aims to determine the radon concentration levels in bottled spring drinking water (BSW) brands commercially sold in Turkey using a radon gas monitor and to assess the internal radiation exposure caused by the ingestion and inhalation of radon. The activity concentrations of radon analyzed in 77 BSW brands varied from 7.1±0.8 to 28.7±2.7 mBq/L with an average of 15.7±5.1 mBq/L. The total annual effective dose was estimated to assess the radiological risk for three age groups in four different scenarios based on annual drinking water intake. All estimated dose values are well below the recommended reference dose of 100 µSv for drinking water. Therefore, radon gas in the investigated BSW samples poses no significant radiological risk to the public.

Determination of potentially toxic metals and natural radionuclides in airborne pollens produced different urban environments in Turkey and health risk assessment.

Air pollutants are associated with potentially toxic metals (PTMs) and natural and/or artificial radionuclides, which can pose a major threat to human and environmental health. Pollens can be utilized as a bioindicator to determine the level of air pollution in urban areas. In this study, the concentrations of PTMs and natural radionuclides in 35 airborne pollen samples of 22 species belonging to Pinaceae, Cupressaceae, Araucariaceae, Betulaceae, Salicaceae, and Oleaceae families grown in different urban areas in Turkey were determined using an energy-dispersive X-ray fluorescence spectrometry. For the first time, non-carcinogenic and radiologic health risk assessments for adults were done, estimating hazard index (HI) and annual effective dose (AED), respectively. The concentrations of Fe, Mn, Zn, Ti, Sr, Cu, Ni, Co, Cr, V and Pb analyzed in airborne pollen samples varied from 52.1 to 3078.0, 26.1 to 159.6, 15.6 to 199.7, 9.1 to 282.2, 1.0 to 128.4, 5.0 to 40.1, 5.4 to 23.6,

222Rn and 220Rn levels in drinking water, emanation, and exhalation assessment, and the related health implications in the U-bearing area of Poli-Cameroon.

The inherent radioactivity of radon gas presents potential exposure risks to human beings through ingestion and inhalation of its radioisotopes 222Rn (radon) and 220Rn (thoron) from water sources. Recent studies have been conducted to assess radon concentrations in different environmental matrices such as water, air, and soil, due to their detrimental impact on human health. As the main cause of lung cancer in non-smokers and an acknowledged contributor to stomach cancer when ingested, the present study aimed to preliminarily assess radon and thoron levels in the Uranium bearing area of Poli in the Faro division of Cameroon, known for its significant U-deposits. The assessment included measuring 220, 222Rn concentrations in drinking water, emanation, and exhalation, with a specific focus on evaluating the exposure of different age groups within the local population. The radon/thoron levels in water and their related exposure and cancer risk data indicated no immediate health hazards. However, continuous monitoring and prospective measures are deemed essential due to the area's abundant U-minerals. The emanation measurements showed sparsely distributed data with a singularity at Salaki, where the equipment recorded values of 8.14 × 1012 Bqm-3 and 3.27 × 1012 Bqm-3 for radon and thoron, respectively. Moreover, radon/thoron transfer coefficients from the soil to the air indicated levels below unity. While the calculated doses suggest minimum potential risk in line with WHO and UNSCEAR guidelines, the obtained results are expected to significantly contribute to the establishment of national standards for radon levels in drinking water, emanation, and exhalation. Furthermore, these findings can play a crucial role in monitoring radon/thoron levels to ensure public health safety.

Radiation dose and lifetime risk for radiation-induced cancer due to natural radioactivity in tap water from Jordan.

The purpose of this study was to investigate the radiological quality of drinking water in Ma'an governorate, which includes the archeological city of Petra and is one of Jordan's most important tourist destinations. To the best of the authors' knowledge, this is the first study in southern Jordan that investigates radioactivity in drinking water and its potential to cause cancer. A liquid scintillation detector was used to measure gross alpha and gross beta activities in tap water samples from Ma'an governorate. A high-purity Germanium detector was used to measure the activity concentrations of 226Ra and 228Ra. Gross alpha, gross beta, 226Ra, and 228Ra activities were < 110-724 mBq/l, < 220-362 mBq/l, < 11-241 mBq/l, and < 32-49 mBq/l, respectively. The results were compared to internationally recommended levels and literature values. Annual effective doses ([Formula: see text]) from 226 and 228Ra intake were calculated for infants, children, and adults. The highest doses were found for children while the lowest were found for infants. For each water sample, the lifetime risk of radiation-induced cancer (LTR) was calculated for the whole population. All of the LTR values were lower than the value recommended by the World Heath Organisation. It is concluded that there are no significant radiation-related health risks associated with consumption of tap water from the studied region.

Study of Polonium (210Po) Activity Concentration in Fruit Wines Derived from Different Locations in Poland.

This study aimed at assessing the activity concentration and the annual effective dose of polonium-210 (210Po) in fruit wines derived from four locations in Poland (Warmian−Masurian, Podlaskie, Lubelskie and Malopolskie voivodeships). The fruit wines differed significantly (p < 0.05) in 210Po activity depending on the production site, with the Malopolskie site having the highest activity (61.4−221.4 mBq/L) and the Podlaskie having the lowest (3.5−97.1 mBq/L). The site differentiation was due to environmental conditions­soil parameters (uranium concentration), precipitations and terrain characteristics, e.g., the proximity of the lakes. The increased activity concentration of 210Po in samples from Malopolska compared with the other sites probably derived from the environment polluted with aqueous wastes and particulate air pollution. The annual effective dose due to the ingestion of fruit wines ranged from 0.112 to 1.214 µSv/year. These levels of exposure are safe according to the WHO criterion (0.1 mSv per year for ingestion) and to the IAEA reference level for public exposure including food (1 mSv per year). Summing up, the data obtained provide information on the activity concentration of 210Po in fruit wines and increase databases on the natural radioactivity of foodstuffs. Future work is needed to examine 210Po activity in samples from all vineyard regions in Poland.

Evaluation of terrestrial radionuclide levels and concomitant radiological risks of bentonites used in many industries.

Bentonite is a soft, porous, easily shaped, and absorbent material rich in aluminum, sodium, and potassium. Bentonite is a mineral widely utilized as drilling mud, ore pelletizing, absorbent/adsorbent, bleaching agent, water impedance, coating, and raw material in various industries. In this study, radiometric measurements of 90 bentonite samples collected from 21 quarries in Turkey were performed using gamma-ray spectrometry. The radiological hazards caused by indoor exposure to adults due to the utilization of bentonites as raw materials in the construction industry and outdoor external exposures to quarry workers were evaluated by estimating the activity concentration index, annual effective doses, and lifetime cancer risk. The average activity concentrations of 226Ra, 232Th and 40K measured in bentonite samples were found as (50 ± 5) Bq/kg, (76 ± 4) Bq/kg and (373 ± 19) Bq/kg, respectively. The evaluation results reveal that the bentonites examined could be safely utilized as raw materials.

Measurement of radium and radon gas in bottled mineral waters.

In this study, the radon gas and radium concentration in the bottled mineral water samples was measured. A total of sixty samples were collected from bottled mineral water sold in the markets in Kahramanmaras. DURRIDGE Rad7 electronic radon detector was used for measurements. Radon and radium activity amounts range from 33.50 ± 1.30 mBq/L to 51.70 ± 2.20 mBq/L, and 2.92 ± 0.15 mBq/L to 4.51 ± 0.26 mBq/L, respectively. Average radon and radium active amounts are 41.67 ± 1.54 mBq/L and 3.63 ± 0.18 mBq/L, respectively. Total annual effective dose values were calculated for these mineral waters according to three different scenarios. In the first of these, it was assumed that natural mineral water was consumed annually instead of 730 L of drinking water (S1). In the second case, 150 L which was the annual average amount of natural mineral water consumed in European Union member countries was used for the annual average amount of natural mineral water consumed by adults (S2). Finally, the annual average amount of natural mineral water consumed in Turkey, 14 L, was used for adults (S3). For scenarios (S1, S2, S3), the total (ingestion + inhalation) annual average dose values ranged from 6.83E-04 mSv/y to 1.05E-03 mSv/y, 1.40E-04 mSv/y to 2.17E-04, and 1.32E-05 mSv/y to 2.03E-05 mSv/y, their average values were 8.49E-04 mSv/y, 1.75E-04 mSv/y, and 1.64E-05 mSv/y, respectively. The total effective dose values calculated within the scope of the current study were below the limit value announced by WHO.

Evaluation of potential radiological hazards of unfired construction materials containing fly ash in Vietnam.

In this study, the specific activities of 226Ra, 232Th and 40K in the unfired construction materials (solid card bricks, 4-hole bricks, pavement bricks) containing fly ash and bottom ash from a coal-fired thermal power plant in Vietnam were measured using the low-level gamma-ray spectrometer with HPGe detector. Also, the 222Rn concentrations in these materials were analyzed using RAD7 radon monitor and then radon mass exhalation rate and emanation fraction of these materials were calculated. The potential radiological hazards for residents living in the model room made of these materials were evaluated. The average specific activity of 226Ra, 232Th and 40K were found as 67.7, 79.3 and 703.5 Bq kg-1, respectively. The total annual effective dose (due to external gamma exposure and internal radon exposure for resident living in the CEN model room made of the unfired brick samples) was found as 0.9 mSv y-1 which is lower than the worldwide average dose of 2.4 mSv y-1. Calculations from ResRad-Build code showed that the doses due to radon exposure account for from 62.3% (at the first year) to 98.8% (at the next 30 years) of the total gamma and radon dose. Under low air exchange to the outside environment, from the 6th year onwards, the total dose may exceed the average dose value from natural radiation exposure sources.

Natural radioactivity in soil samples taken from Kahramanmaras provincial center.

The levels of 238U, 232Th, and 40K with gross alpha and beta values in soils collected from the Kahramanmaras city center were measured in this study, and the annual effective dose equivalent (AEDE), excessive lifetime cancer risk (ELCR), and terrestrial absorbed gamma dose rates were calculated for gamma radiation from 238U, 232Th, and 40K radionuclides. The samples' gross alpha and beta radioactivity concentrations, respectively, range from 0.06 ± 0.01 Bq/kg to 0.45 ± 0.04 Bq/kg and 0.14 ± 0.02 Bq/kg to 0.95 ± 0.09 Bq/kg. The Kahramanmaras province's soil samples have mean gross alpha and beta radiation values of 0.25 ± 0.03 Bq/kg and 0.52 ± 0.05 Bq/kg, respectively. 238U, 232Th, and 40K activity concentrations in soil samples range from 2.32 ± 0.2 Bq/kg to 40.10 ± 1.4 Bq/kg, 0.60 ± 0.03 Bq/kg to 10.47 ± 1.01 Bq/kg, and 11.60 ± 1.01 Bq/kg to 160.84 ± 4.6 Bq/kg, respectively. 238U, 232Th, and 40K each had average activity concentrations of 11.50 ± 1.1, 4.50 ± 0.4, and 62.20 ± 1.6 Bq/kg in soil, respectively. The annual effective dose equivalent (AEDE), excessive lifetime cancer risk (ELCR), and terrestrial absorbed gamma dose rate range from 0.01 ± 0.01 µSv y-1 to 0.03 ± 0.02 µSv y-1, and 0.01 ± 0.01 × 10-3 to 0.12 ± 0.03 × 10-3, 1.72 ± 0.01 nGy h-1 to 25.05 ± 0.21 nGy h-1, respectively. Additionally, the average annual effective dose equivalent (AEDE), average excessive lifetime cancer risk (ELCR), and average terrestrial absorbed gamma dose rates are 0.01 ± 0.01 µSv y-1, and 0.05 ± 0.02 × 10-3, 9.81 ± 0.09 nGy h-1, respectively. The acquired data were compared to both domestic and international standards.

Radioactivity amounts, annual effective dose rate, and lifetime cancer risk estimation of some vegetable and fruit samples cultivated in Kahramanmaras, Turkey.

In this research, examples of the fruits and vegetables cultivated in Kahramanmaras, 238U, 232Th, and 40K levels, were detected, and in the case of consumption of these vegetables and fruits, for several age categories (adults, children (10 years old), and infants), annually effective dose rates and lifetime cancer risks were calculated. In fruit samples, concentrations of 238U, 232Th, and 40K ranged from under detection limit (UDL) to 15.29 ± 1.14 Bq/kg, 0.30 ± 0.01 to 13.23 ± 1.60 Bq/kg, and 5.82 ± 0.21 to 179.82 ± 1.34 Bq/kg, respectively. The mean concentrations of 238U, 232Th, and 40K in fruit samples were 5.31 ± 0.44 Bq/kg, 2.72 ± 0.26 Bq/kg, and 56.84 ± 0.57 Bq/kg, respectively. In vegetable samples, concentrations of 238U, 232Th, and 40K ranged from 0.48 ± 0.04 to 11.77 ± 0.95 Bq/kg, 0.55 ± 0.04 to 4.57 ± 0.44 Bq/kg, and 9.32 ± 0.43 to 52.44 ± 0.52 Bq/kg, respectively. The mean concentrations of 238U, 232Th, and 40K in the vegetable samples were 6.58 ± 0.65 Bq/kg, 2.72 ± 0.27 Bq/kg, and 27.09 ± 0.27 Bq/kg, respectively. The mean annual effective dose rates for adults, children (10 years old), and infants in fruit samples were 0.184 ± 0.001 mSv/y, 0.288 ± 0.002 mSv/y, and 0.304 ± 0.003 mSv/y, respectively. The average lifetime cancer risks for adults, children (10 years old), and infants in fruit samples were 0.647 ± 0.006 × 10-4, 1.011 ± 0.010 × 10-4, and 1.067 ± 0.010 × 10-4, respectively. The mean annual effective dose rates for adults, children (10 years old), and infants in the vegetable samples were 0.118 ± 0.001 mSv/y, 0.128 ± 0.001 mSv/y, and 0.086 ± 0.001 mSv/y, respectively. The mean lifetime cancer risks for adults, children (10 years old), and infants in vegetable samples were 0.416 ± 0.004 × 10-4, 0.449 ± 0.004 × 10-4, and 0.304 ± 0.003 × 10-4, respectively.

Radiation doses due to smoking different types of tobacco leaves grown in Turkey.

The activity concentrations of 238U, 232Th, 40 K and 137Cs radionuclides in 25 samples of tobacco leaves grown in Turkey have been measured using a high purity co-axial germanium detector. The measured activity concentrations for 238U ranged from 3.6 to 22.5 Bq kg-1 with an average of 9.8 Bq kg-1, for 232Th from 0.8 to 11.0 Bq kg-1 with an average of 2.4 Bq kg-1, and for 40 K from 360.3 to 1,479.5 Bq kg-1 with an average of 810.0 Bq kg-1. The concentrations of 137Cs, the residue of fallout from the Chernobyl reactor accident, were found to range from 0.2 to 2.1 Bq kg-1 with an average of 0.5 Bq kg-1. The results indicate that the average activity concentrations of 238U and 232Th lie within the range of measured values worldwide, whereas for 40 K the average was found to be higher. The average annual effective radiation doses from the inhalation of the corresponding tobacco smoke by an adult smoking 20 cigarettes per day was deduced to be 93.3 µSv y-1 for 238U, 193.2 µSv y-1 for 232Th, 5.6 µSv y-1 for 40 K, and 292.1 µSv y-1 in total. The average annual effective dose from 137Cs was calculated to be 8.5 nSv y-1. The resulting average annual effective radiation doses of 0.3 mSv due to the inhalation of natural radiation sources in tobacco were compared with studies worldwide and found much smaller than the worldwide average effective dose of 1.26 mSv. It is concluded that smoking may contribute a non-negligible fraction to the annual effective dose depending on cigarette consumption and activity concentration in tobacco. This study is the first in which natural and anthropogenic radioactivity in tobacco in Turkey was measured. Therefore, it is considered as a baseline study. Further studies are needed to investigate the role of tobacco refinement in the observed reduction of 238U concentration of refined tobacco.

Soil to tobacco component transfer factors for natural radionuclides 40K, 226Ra, and 232Th and the risk assessment of tobacco leaf in smoking.

This study determined the activity concentrations and corresponding transfer factors (TF) of 40K, 226Ra, and 232Th in three tobacco components (root, stem, and leaf). The radiation hazard index parameters were assessed for the tobacco leaf. The activity concentrations in the soil were 589-762, 32-43, and 49-59 Bq kg-dw-1 (dry weight) for 40K, 226Ra, and 232Th, respectively. The average activity concentrations of 40K, 226Ra, and 232Th were 447, 5.41 and 5.69 Bq/kg-dw for the root, 670, 9.64 and 7.61 Bq kg-dw-1 for the stem, and 793, 6.79 and 6.15 Bq kg-dw-1 for the leaf, respectively. The TF values were 0.42-1.42, 0.10-0.49 and 0.06-0.23 for 40K, 226Ra, and 232Th, respectively. The stem and leaf 40K TF values were significantly higher than the root values. The stem 226Ra TF values were significantly higher than the root values. The 226Ra and 232Th activity concentrations and TFs of tobacco components had a significant positive correlation. Based on the activity concentrations of the tobacco leaves, the annual inhalation effective dose to the lungs for an adult smoker was 0.32-0.81 mSv y-1 (average 0.60 mSv y-1). The Excess Lifetime Cancer Risk (ELCR) caused by smoking was an average of 2.39 × 10-3.

[Analysis on individual dosage monitoring of some interventional radiology staffs in Tianjin City from 2016 to 2020].

Objective: To investigate the individual external dose level of some interventional radiology staffs from 2016 to 2020 in Tianjin City. Methods: All 2068 interventional radiology staffs who were included in the work of the Radiation Monitoring Project from 2016 to 2020 were selected as study subjects in March 2021. The individual dose monitoring results of interventional radiology staffs of different ages, working years, time and medical institutions were analyzed. Results: Among 2068 interventional radiology workers, 1406 (67.99%) were male and 662 (32.01%) were female. The age was 44.6 (39.2, 50.3) years, and the working years was 10.5 (4.3, 14.6) years. The annual effective doses per capita of 40-49 age group and ≥50 age group were higher than that of 30-39 age group (P<0.05) . The annual effective dose per capita of 5-9 working years was higher than that of <5 working years, and the annual effective dose per capita of 10-29 working years was higher than that of 5-9 working years (P<0.05) . The median per capita annual effective dose of the interventional radiology staffs was 0.164 mSv. There were 1976 interventional radiology staffs with an annual effective dose of <0.50 mSv/a (95.6%) . The collective dose distribution ration SR(0.5) was 41.1%. The difference of effective dose per capita in each year was statistically significant (H=19.23, P<0.05) . The per capita annual effective dose of interventional radiology staffs in tertiary medical institutions was higher than that in secondary medical institutions, and the difference was statistically significant (P<0.05) . Conclusion: The personal dose of interventional radiology staffs in Tianjin City is at a low level. It is necessary to emphasize the radiation hazard protection of interventional radiology staffs in tertiary medical institutions, 40-49 years old, ≥50 years old age groups and 5-9, 10-29 working years groups.

Assessment of background radiation levels in the southeast of Iran.

Background: Measuring background radiation (BR) is highly important from different perspectives, especially from that of human health. This study was conducted to measure BR in the southeast of Iran. Methods: BR was measured in Hormozgan and Sistan-Bluchestan provinces using portable Environmental Radiation Meter Type 6- 80 detector. The average value was used to calculate the absorbed dose rate and indoor annual effective dose (AED) from BR. In addition, excess lifetime cancer risk (ELCR) was evaluated. Results: The results showed that the maximum and minimum absorbed dose rates were 71.9 and 34.2 nGy.h-1 in Abomoosa and Minab in Hormozgan province and 90.0 and 47.8 nGy.h-1 in Zahedan and Chabahar in Sistan-Bluchestan province, respectively. Data indicated that these areas had a lower BR level compared with the worldwide level. The ELCR from indoor AED was larger compared with the worldwide average of 0.29 × 10-3. Conclusion: This study provided a reference for designing and developing specific regional surveys associated with the measurement of natural BR in the southeast of Iran.

Assessment of radiation dose from radon ingestion and inhalation in commercially bottled drinking water and its annual effective dose in Eastern Province, Saudi Arabia.

The isotopes of radium, uranium, polonium, lead, and short-lived radon are the common radionuclides found in drinking water. The abnormal amount of radon in drinking water causes health risks. In this study, an attempt has been made to estimate the level of radon concentrations and its annual effective dose from bottled water brands and tap drinking water. A total of 77 samples of drinking water sources; 47 bottled water brands and 27 tap water samples including 3 samples from water storage tank supplier were collected and examined. The measurements were performed using active detection method technique called Durridge RAD7-H2O with closed loop. The minimum and maximum level of average radon concentrations was 0.10 ± 0.02 BqL-1 and 9.2 ± 0.02 BqL-1. The results were below the limit recommended by the Environmental Protection Agency (11 BqL-1). The annual effective dose for children and adults was in the range from almost 0.51 µSvy-1 to 46.69 µSvy-1. There are no indications of significant threat from radon concentrations in bottled water brands or tap drinking water, and it is safe as far as health hazard is concerned.

Assessment of radon concentration and heavy metal contamination in groundwater of Udhampur district, Jammu & Kashmir, India.

Radon concentration was measured in water samples of 41 different locations from Udhampur district of Jammu & Kashmir, India, by using RAD7 and Smart RnDuo monitor. The variation of radon concentration in water ranged from 1.44 ± 0.31 to 63.64 ± 2.88 Bq L-1, with a mean value of 28.73 Bq L-1 using RAD7 and 0.64 ± 0.28 to 52.65 ± 2.50 Bq L-1, with a mean value of 20.30 Bq L-1 using Smart RnDuo monitor, respectively. About 17.07% of the studied water samples recorded to display elevated radon concentration above the reference range suggested by United Nation Scientific Committee on the Effects of Atomic Radiations (UNSCEAR). The mean annual effective dose of these samples was determined, and 78.95% samples were found to be within the safe limits set by World Health Organisation (WHO) and European Council (EU). The study revealed good agreement between the values obtained with two methods. Heavy metals (Zn, Cd, Fe, Cu, Ni, As, Hg, Co, Pb and Cr) were determined in water samples by microwave plasma atomic emission spectrometer, and their correlation with radon content was also analysed.

Indoor ²²²Rn levels and effective dose estimation of academic staff in Izmir, Turkey.

OBJECTIVE: To investigate the annual effective doses from indoor radon received by academic staff in the Faculty building. METHODS: Measurements of indoor radon concentrations were performed in the Arts and Sciences Faculty of Dokuz Eylül University for two surveys of about 1 month duration respectively using the SSNTD (Solid State Nuclear Track Detectors) method with LR115 detectors. Time integrated measurements comprised different locations inside the faculty building: classrooms, toilets, canteen and offices. Homes of academic staff were also tested for radon. RESULTS: The arithmetic mean radon concentration is 161 Bq m-3 with a range between 40 and 335 Bq m-3 in the Faculty. Six offices and three classrooms have a radon concentration above 200 Bq m-3. The results show that the radon concentration in classrooms is generally higher than in offices. Based on the measured indoor radon data, the annual effective doses received by staff in the Faculty were estimated to range from 0.79 to 4.27 mSv, according to UNSCEAR methodology. The annual effective doses received by staff ranged from 0.78 to 4.20 mSv in homes. On average, the Faculty contributed 56% to the annual effective dose. CONCLUSION: Reported values for radon concentrations and corresponding doses are within the ICRP recommended limits for workplaces.

Assessment of natural and artificial radioactivity concentrations in infant powdered milk consumed in Albania and estimation of the annual effective dose.

This study evaluates the radiological risk associated with the consumption of infant powdered milk in Albania. Infant powdered milk is the basic foodstuff for their growth and development in many countries around the world. The activity concentration of radionuclides (40K, 226Ra, 232Th and 137Cs) was measured in fourteen types by using the gamma-ray technique. The results indicated that the activity concentration of 40K, 226Ra and 232Th were detected in all selected samples, whereas 137Cs were not detected in most of them. The activity concentration of 40K, 226Ra and 232Th varies from 92.83 ± 4.32 to 400.53 ± 17.00 Bq kg-1, 0.80 ± 0.15 to 4.91 ± 0.28 Bq kg-1 and 0.19 ± 0.02 to 1.89 ± 0.14 Bq kg-1, respectively. The highest value for 137Cs was found to be 0.36 ± 0.03 Bq kg-1. The average values of Annual Effective Dose (AED) due to consumption of powdered milk were found to be 664.54 ± 31.11 µSv y-1 for infants ≤1 year and 138.53 ± 5.40 µSv y-1 for infants 1-2 years. The values of dose in this study were lower than the recommended limit of 1 mSv y-1 set by WHO/FAO and ICRP for all ages. Therefore, brands of powdered milk are safe, so, these can be normally consumed by infants in Albania.

Review of natural radioactivity in tobacco cigarette brands.

Cigarettes smoking are leading causes of lung cancer in the world. In several countries, the radioactivity of tobaccos cigarette brands has been evaluated to estimate the effective dose from smoking inhalation. In this paper, we have reviewed 40 researched papers of radioactivity in tobacco cigarette brands by searching specified databases from various search engines such as Web of Science, Google Scholar, Scopus, Science Direct and PubMed for the studies published between the year 2000 and November, 2023 in English language. Results show that, the arithmetic mean and range of radioactivity concentration in mBq/g were 20.4 (0.4-128.6), 15.4 (2.0-78.8), 630.8 (1.2-1330.0), 8.1 (0.3-41.0), 15.2 (0.2-82.0) and 5.9 (2.0-16.0) from 210Po, 210Pb, 40K, 232Th and 232U and 226Ra, respectively. The annual effective doses were also estimated using the assumption that a smoker smokes 20 cigarettes per day. The mean annual effective doses in µSv/y from 210Po, 210Pb, 40K, 232Th and 232U and 226Ra were 295, 74.1, 5.80, 889.7, 192.6 and 90.1, respectively. The mean annual effective dose is lower than the reference level 1000 to 20000 µSv/y for existing situation in ICRP Publication 103. The average value of ELCR is 1.03 ×10-3, 0.26 ×10-3,0.02 ×10-3,3.11 ×10-3,0.67 ×10-3 and 0.32 ×10-3 for 210Po, 210Pb, 40K, 232Th and 232U and 226Ra, respectively. The ELCR values obtained in this study are well below the world average value of 1.45 ×10-3. The mean value of LCC in per million is 5.3, 1.3, 0.1, 16, 3.5 and 1.6 for 210Po, 210Pb, 40K, 232Th and 232U and 226Ra, respectively. The values of LCC obtained in this study are all below the limit range of 170-230 per million persons. The result shows 232Th contribute much larger for annual effective dose, annual equivalent dose, ELCR and LCC for smoking tobacco cigarette brands compared to other radionuclides. More studies in radioactivity in tobacco cigarette brands from different countries are required to have conclusive mean annual effective dose, annual equivalent dose, ELCR and LCC for each natural radionuclide.