Activity Concentrations In Soil Samples Research Articles

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.

Determination of natural radioactivity, hazard parameters and physico-chemical properties of soils from Palakkad-Thrissur district, Kerala, India

Assessment of natural radioactivity (226Ra, 232Th, and 40K) and related radiation hazards play an important role in human health research and have received much attention from worldwide researchers. Soil is one of the key sources of human exposure to ionizing radiations. There has recently been a growing demand for soil data and information. This study aims to assess the radioactivity concentration and related parameters in the environment of Kuthiran hills due to radionuclides in soil samples collected from various locations around the Thrissur-Palakkad Highway (NH-544) regions in Kerala state (India). The activity concentrations of soil samples were determined by a gamma ray spectrometry system consisting of a p-type HPGe detector, with relative efficiency of 40%. The mean activity concentrations of 226Ra, 232Th and 40K were found to be 47.24 Bqkg−1, 67.49 Bqkg−1, and 810.87 Bqkg−1, respectively. These values are well within the permissible range, as recommended by the UNSCEAR 2008. The soil samples with the highest activity concentrations were primarily found in the valley region. The calculated hazard indices were used to estimate the potential radiological health risk from the soil, and the dose rates associated with it are significantly lower than their permissible limit. The overall findings indicate no radiological threat to the population's health in the study area.

Evaluation of naturally occurring radioactive materials (NORM) in the soil, in a potential area for unconventional reservoirs in the Rancheria Sub-Basin

Naturally occurring radioactive elements depend on lithology geogenic characteristics, such as depositional, environmental, or diagenetic. Thus, evaluating these elements constitutes a tool to define ionizing radiation effect from rocky sequences. This study carried out in the Rancheria Sub-Basin establishes both characterization and assessment of this kind of material, known as NORM. The sampling included uranium-238, thorium-232, potassium-40, radon-226, and radon-222 in soil samples, cutting samples from the Molino-1 well, and radon in surface water. Bases on a radiometric methodology with a gamma-ray spectrometer for uranium-238, thorium-232, and potassium-40 and emanometric with ionizing chambers for radio-226 and radon-222. The analysis and results of the activity concentrations in soil samples of U-238, Th-232, K-40, and Ra-226 are 11.7 BqKg−1, 33.0 BqKg−1, 424.5 BqKg−1, and 15.59 BqKg-1, respectively, among the acceptable global averages. However, in some areas, observed values indicate high activity concentrations of U-238, Th-232, K-40, Ra-226, and Rn-222 in the soil of 50.2 BqKg−1, 62.8 BqKg−1, 1596.3 BqKg−1, 44.25 BqKg−1, and 112546.79 Bqm−3, respectively. Those activity concentrations were associated with zone lithology.

Assessment of the radiological situation in different areas affected by uranium mining and uranium processing in the Czech Republic

This study presents measurements of activity concentrations of natural radionuclides in selected water and soil samples taken from areas affected by the uranium industry in the surroundings of Pribram, Straz pod Ralskem and Mydlovary, Czech Republic. In these areas, the dose equivalent rate was also determined at the sampling locations and additionally also during walkabouts in the surroundings of sludge fields. The activity concentration of water samples was 0.06 ? 0.02 BqL?1 for 226Ra and 0.07 ? 0.07 mgL?1 for 238U while the mean activity concentrations of soil samples were 74 ? 70 Bqkg?1 and 80 ? 77 Bqkg?1 for 226Ra and 238U, respectively. The average value of the dose equivalent rate was of 0.15 ? 0.1 ?Svh?1. These values conform with the nature of the industrial activities which were carried out in the areas and are comparable with measurement results in similar locations worldwide.

Assessment of radiological safety of abandoned tantalite mining sites in Oke-Ogun, Oyo State, Nigeria

Introduction: Tantalite and other solid mineral deposits in Oke-Ogun occupy a very large landscape, and the possibilities of further exploration in new landscape and abandoning unproductive sites cannot be ruled out. These landscapes when abandoned become hideout for criminals and ritualistic activities which pose a great threat to the wellness of the people in the area and Nigerians at large. Objectives: This study attempts to investigate the radiological safety of these abandoned mines so as to convert them to economical valuable sites that can serve as a means of employment for population of the unemployed youth in the area and Nigeria at large. Materials and Methods: A total of seventeen soil samples were randomly selected. These samples were processed and analyzed for activity concentrations of 226Ra, 232Th, and 40K using Hyper Pure Germanium Gamma Spectrometer. RESidual RADioactivity software version (6.5), a computer program developed by the Environmental Assessment Division of Argonne National Laboratory, was used for dose prediction for 70 years using the activity concentrations of soil samples from all the selected sites as its input parameter for the software. Predicted doses were estimated with respect to the three exposure pathways, namely external gamma irradiation from radionuclides in the soil samples, inhalation of dust particles, and inadvertent ingestion of soil. Results: The measured activity concentrations of radionuclides: 226Ra for all the sites is in the range of (17–177) Bq/kg, 232Th in the range of (2–107) Bq/kg, and 40K in the range of (650–1667) Bq/kg. The predicted dose for all the sites is within the range of 0.05–0.35 mSv/y with Eluku mining site having values greater than the permissible limit of 0.25 mSv/y. The health implication of these values is that three of the sites (Gbedu, Sepenteri, and Komu) are safe for other usages. Conclusion: Any of these three mining sites may be used for re-creational purposes, fishing and building of estates to mention but a few.

Determination of radioactivity concentrations in soil samples and dose assessment for Rize Province, Turkey

In this study, the activity concentrations of naturally occurring 40K, 238U, and 232Th radionuclides and of the artificial, Chernobyl accident-induced 137Cs radionuclide were measured in soil samples collected from Rize Province in the Black Sea region of Turkey.Rize is a city located in the Northeastern District of Turkey, which was significantly affected by the 1986 Chernobyl nuclear reactor accident in Ukraine, and the effects have continued to today. Tea is the main production plant of the region, and was contaminated by the artificial radioactivity. Therefore, measurements of residual 137Cs contamination in soil are critical for monitoring the potential impacts on human health.The activity concentrations of radionuclides in 24 soil samples from the study area were measured by means of gamma spectrometry with a Nal(TI) detector. The activity concentrations in soil samples varied in the range of 7.4–79.8 Bq kg−1 for 238U, 9.5–170.8 Bq kg−1 for 232Th, 35.7–913.8 Bq kg−1 for 40K, and 0.6–154.3 Bq kg−1 for 137Cs. The gamma absorbed dose rates in air were in the range of 10.7–156.4 nGy h−1, with an arithmetic mean of 56.9 nGy h−1, while the annual effective dose rates were determined to be in the range of 13.1–191.8 μSv y−1. The calculated values of external hazard index (Hex) for the soil samples in the study area were in the range of 0.12–0.94. The average value of radium equivalent activity was 125.0 Bq kg−1.The activity concentrations of radionuclides in soil samples were compared to the international values reported by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR, 2000) and previous studies on the area.

EFFECTIVE DOSE DUE TO TERRESTRIAL GAMMA RADIATION ESTIMATED IN SOUTHERN VIETNAM BY CAR-BORNE SURVEY TECHNIQUE.

Absorbed dose rates in air from natural radionuclides were measured by a car-borne survey in southern Vietnam. The mean absorbed dose rate in air for southern Vietnam, which consists of the south-east region and the Mekong River Delta region, was 64 ± 18 nGy h-1, while rates for the two regions were 61 ± 17 and 66 ± 19 nGy h-1, respectively. These dose rates were respectively 1.2, 2.1 and 0.9 times the measured values that were calculated on the basis of activity concentrations of soil samples in a previous study. It was considered that measured dose rate in the south-east region was influenced by the presence of artificial structures such as high-rise buildings and roads. The effective dose due to terrestrial gamma radiation for southern Vietnam was calculated to be 0.55 mSv y-1 which is 1.2 times higher than the world-wide average of 0.48 mSv y-1.

Study of soil gas radon variations in the tectonically active Dharamshala and Chamba regions, Himachal Pradesh, India

Soil gas radon measurements were made in Chamba and Dharamshala regions of Himachal Pradesh, India, to study the correlation, if any, between the soil gas radon, radium activity concentration of soil, and the geology/active tectonics of the study region. Soil gas radon surveys were conducted around the local fault zones to check their tectonic activities using the soil gas technique. Soil gas radon activity concentration at thirty-five different locations in Dharamshala region has been found to be varying from 13.2 ± 1.5 to 110.8 ± 5.0 kBq m−3 with a geometrical mean of 35.9 kBq m−3 and geometrical standard deviation of 1.8. Radon activity concentration observed in the thirty-seven soil gas samples collected from the Chamba region of Himachal Pradesh varies from 5.2 ± 1.0 to 35.6 ± 2.5 kBq m−3, with geometrical mean of 15.8 kBq m−3 and geometrical standard deviation of 1.6. Average radium activity concentrations in thirty-four soil samples collected from different geological formations of Dharamshala region and Chamba region are found to be 40.4 ± 17 and 38.6 ± 1.7 Bq kg−1, respectively. It has been observed that soil gas radon activity concentration has a wide range of variation in both Dharamshala and Chamba regions, while radium activity concentrations in soil samples are more or less same in both the regions. Moreover, soil gas radon activity concentration has a better positive correlation with the radium activity concentration in soil samples collected from Chamba region as compared to Dharamshala region.

Assessment of soil contamination by 210Po and 210Pb around heavy oil and natural gas fired power plants

Soil contamination by 210Pb and 210Po around heavy oil and natural gas power plants has been investigated; fly and bottom ash containing enhanced levels of 210Pb and 210Po were found to be the main source of surface soil contamination. The results showed that 210Pb and 210Po in fly-ash (economizer, superheater) is highly enriched with 210Pb and 210Po, while bottom-ash (boiler) is depleted. The highest 210Pb and 210Po activity concentrations were found to be in economizer ash, whereas the lowest activity concentration was in the recirculator ash. On the other hand, 210Pb and 210Po activity concentrations in soil samples were found to be higher inside the plant site area than those samples collected from surrounding areas. The highest levels were found in the vicinity of Mhardeh and Tishreen power plants; both plants are operated by heavy oil and natural fuels, while the lowest values were found to be in those samples collected from Nasrieh power plant, which is only operated by one type of fuel, viz. natural gas. In addition, the levels of surface soil contamination have decreased as the distance from the power plant site center increased.

Determination of gamma radioactivity levels and associated dose rates of soil samples of the Akkuyu/Mersin using high-resolution gamma-ray spectrometry

In this study several soil samples were collected from the Büyükeceli district where Turkey's first nuclear power plant will be built and radioactivity concentrations of (226)Ra, (232)Th, (40)K and (137)Cs were determined by gamma spectrometry using a high-purity germanium detector. The measured activity concentrations in soil samples ranged from 9.8 ± 0.7 to 258.6 ± 15.8, 11.7 ± 0.9 to 85.6 ± 5.0, 173.8 ± 2.1 to 1949.5 ± 14.7 and 0.4 ± 0.1 to 72.2 ± 2.2 Bq kg(-1) for (226)Ra, (232)Th, (40)K and (137)Cs, respectively. Findings are in good agreement with the published results of neighbouring areas. The absorbed gamma dose rate (D) in air and the annual effective dose of soil samples were calculated to be 80.2 nGy h(-1) and 98.3 mSv y(-1), respectively. The results show that the radiation hazard in the Büyükeceli district is insignificant. The data presented in this study would be very useful to determine the future effects of the nuclear power plant to the environment.

Assessment of natural and fallout radioactivity in soil samples of Visakhapatnam

Environmental gamma radiation levels around the new Bhabha Atomic Research Centre site at Visakhapatnam have been assessed. Natural and anthropogenic radionuclide activity concentrations in soil samples collected were determined using high-resolution gamma spectroscopy. Average activity concentrations of 238U, 226Ra, 232Th and 40K were found to be 38, 38, 230 and 520 Bq kg−1, respectively. No anthropogenic radionuclide except fallout 137Cs having mean concentration range ≤ 0.2–2.2 Bq kg−1 was detected in the soil samples. The observed values are compared with the values reported for different areas in India and other parts of the world. The annual total external gamma radiation dose to the members of public estimated using the above observations ranged from 0.13 to 0.38 mSv y−1 with an average of 0.25 mSv y−1.

First measurements of 238Pu and 238Pu/137Cs activity ratio in Montenegro soil

Plutonium-238 (238Pu) activity concentrations in soil samples from Montenegro (six samples from three localities) have been measured for the first time. The 238Pu/137Cs activity ratio was determined on the basis of alpha and gamma-spectrometric measurements, and found to be with an average of 0.0006 and standard deviation of 0.0003. By using the activity ratios determined in the present study, 238Pu activity concentrations were estimated for three localities in the central: one in the northern, and two in the eastern part of Montenegro.

Estimation of radioactive contamination of soils from the “Balapan” and the “Experimental field” technical areas of the Semipalatinsk nuclear test site

In spite of the long history of the research, radioactive contamination of the Semipalatinsk nuclear test site (SNTS) in the Republic of Kazakhstan has not been adequately characterized. Our cartographic investigation has demonstrated highly variable radioactive contamination of the SNTS. The Cs-137, Sr-90, Eu-152, Eu-154, Co-60, and Am-241 activity concentrations in soil samples from the “Balapan” site were 42.6–17646, 96–18250, 1.05–11222, 0.6–4865, 0.23–4893, and 1.2–1037 Bq kg−1, correspondingly. Cs-137 and Sr-90 activity concentrations in soil samples from the “Experimental field” site were varied from 87 up to 400 and from 94 up to 1000 Bq kg−1, respectively. Activity concentrations of Co-60, Eu-152, and Eu-154 were lower than the minimum detectable activity of the method used. Concentrations of naturally occurring radionuclides (K-40, Ra-226, U-238, and Th-232) in the majority of soil samples from the “Balapan” and the “Experimental field” sites did not exceed typical for surrounding of the SNTS areas levels. Estimation of risks associated with radioactive contamination based on the IAEA clearance levels for a number of key radionuclides in solid materials shows that soils sampled from the "Balapan" and the “Experimental field” sites might be considered as radioactive wastes. Decrease in specific activity of soil from the sites studied up to safety levels due to Co-60, Cs-137, Sr-90, Eu-152, Eu-154 radioactive decay and Am-241 accumulation-decay will occur not earlier than 100 years. In contrast, soils from the “Experimental field” and the “Balapan” sites (except 0.5–2.5 km distance from the “Chagan” explosion point) cannot be regarded as the radioactive wastes according safety norms valid in Russia and Kazakhstan.

Investigation of radioactivity level in soil and drinking water samples collected from the city of Erzincan, Turkey

This study is part of an effort to assess the level of background radiation for Erzincan Province of eastern Turkey. Radionuclide activity concentrations in soil samples were measured through gamma-ray spectrometry and the average activities were determined as 8.93, 11.39, 281.94, and 9.52 Bq/kg for the radionuclides 238U, 232Th, 40K, and 137Cs, respectively. The average annual effective dose from these natural radioactivity sources (238U series, 232Th series and 40K,) was calculated to be 27.9 μSv. Radioactivity levels in drinking and potable water samples were studied using a multi-channel low level proportional counter. The average gross alpha activity concentration was found to be 0.0477 Bq/L (min. 0.007 Bq/L; max. 0.421 Bq/L) and the average gross beta activity was measured as 0.104 Bq/L (min. 0.008 Bq/L; max. 1.806 Bq/L). These values lead to an average annual effective dose of 9.75 μSv from the alpha emitters and 56.34 μSv from the beta emitting radionuclides in water. The radioactivity levels in the water samples investigated were found to comply with the reference levels recommended by WHO and the regulations set forth by the Turkish Health Ministry.

A study of environmental radioactivity measurements for Cankiri, Turkey

This study is the first to assess the level of background radiation for the Cankiri province of Turkey. Indoor air radon concentrations were determined using Columbia Resin-39 nuclear track detectors and the average (222)Rn activity was found to be 44 Bq m(-3) (equivalent to an annual effective dose of 1.1 mSv). Measurements of gamma doses in outdoor air were performed using a portable plastic scintillation detector and the average gamma absorbed dose rate was found to be 8 μR h(-1) (corresponding to an annual effective dose of 87.7 μSv). Radionuclide activity concentrations in soil samples were measured through gamma-ray spectrometry and the average activities were determined as 17.7, 22.3, 357 and 4.1 Bq kg(-1) for the radionuclides (238)U, (232)Th, (40)K and (137)Cs, respectively. The average annual effective dose from the natural radioactivity sources ((238)U series, (232)Th series and (40)K) was calculated to be 44.4 μSv. Radioactivity levels of drinking water samples were carried out using a low-background proportional counter and the average gross alpha and beta activities were obtained as 0.25 and 0.26 Bq l(-1), respectively (equivalent to an annual effective dose of 184 μSv). The average radon concentrations in indoor air and the average radionuclide activities in soil were found to be lower than most Turkish cities while higher levels of outdoor gamma dose rate and water radioactivity were observed. The results of this study showed that the region's background radioactivity level differs considerably from the reported data for Turkish cities.

Assessment of natural radioactivity concentrations and gamma dose rate levels in Kayseri, Turkey

This study assesses the level of background radiation for Kayseri province of Turkey. Natural radionuclide activity concentrations in soil samples were determined using high-resolution gamma spectroscopy. Outdoor gamma dose measurements in air at 1 m above ground level were determined using a portable gamma scintillation detector. The obtained results of uranium and thorium series as well as potassium ((40)K) are discussed. The present data were compared with the data obtained from different areas in Turkey. From the measured gamma-ray spectra, the average activity concentrations were determined for (238)U (range from 3.91 to 794.25 Bq kg(-1)), (232)Th (range from 0.68 to 245.55 Bq kg(-1)) and (40)K (range from 23.68 to 2718.71 Bq kg(-1)). The average activity concentrations of (238)U, (232)Th and (40)K were found to be 35.51, 37.27 and 429.66 Bq kg(-1), respectively, and 11.53 Bq kg(-1) for the fission product (137)Cs. The highest values of (238)U, (232)Th and (40)K concentrations (794.25 Bq kg(-1), 245.55 Bq kg(-1), 2718.71 Bq kg(-1), respectively) were observed in abnormal samples at Hayriye village. The average outdoor gamma dose rate in air at 1 m above the ground was determined as 114.43 nGy h(-1). Using the data obtained in this study, the average annual effective dose for a person living in Kayseri was found to be about 140.34 µSv.

Gamma ray concentrations in soil and building materials in Ordu, Turkey

The city of Ordu is in the Eastern Black Sea region of Turkey with a population of approximately 716,000. Presently there is no information available about radioactivity levels in Ordu soil and building materials. For this reason, activity concentrations in soil and building material samples collected from different sampling stations in Ordu were measured using gamma-ray spectrometry. In addition to natural radionuclides, 137Cs was detected in the soil samples and the possible origins of this radionuclide were discussed. The activity concentrations of soil samples ranged from 13.4 to 151.7 Bq kg−1 for 226Ra, from 14.3 to 98.5 Bq kg−1 for 232Th, from 303 to 1107 Bq kg−1 for 40K and from 67.4 to 275.3 Bq kg−1 for 137Cs. The mean concentrations of 226Ra, 232Th and 40K in selected building materials were 34.5, 26.9 and 378.4 Bq kg−1, respectively. The results were compared with the reported data from different works. From the measurements, radium equivalent activity, terrestrial absorbed dose, annual effective dose rate, external hazard indices and internal hazard indices were calculated, and were found to be within the acceptable limits. The data presented in this study might be useful as a baseline data for future estimations of a population's exposure.

Occupational exposure to natural radionuclides due to mining activities in Ibadan, Southwestern Nigeria

The activity concentrations of potassium, uranium and thorium in minerals and soil samples from a mining site in Ibadan, Southwestern Nigeria were measured using gamma ray spectroscopy method. Effective dose per annum has been calculated from the activity concentrations of dominant gamma-emitting natural radionuclides, potassium, uranium and thorium. Samples collected include minerals (beryl, quartz and feldspar), soil samples from the mining pits, heaps and undisturbed land around the mining site. The activity concentrations of 40 K, 238 U and 232 Th, respectively in Bq kg -1 in the mineral samples were as follows: 1985 ± 16, 4.8 ± 0.9 and 11.8 ± 5.8 for beryl sample, 115.1 ± 27.9, 5.0 ± 1.3 and 6.3 ± 5.0 for feldspar samples and 1421 ± 122, <4.8 and 20.1 ± 3.5 for quartz samples. For the soil samples, the mean activity concentrations of 40 K, 238 U and 232 Th, respectively, were 314.2 ± 5.7, 27.7 ± 2.6 and 11.5 ± 5.9 Bq kg -1 for soil samples from the pits and 278.1 ± 5.4, 21.1 ± 2.0 and 15.3 ± 7.5 Bq kg -1 for soil samples from heaps. The mean activity concentrations of soil samples from the undisturbed land around the mining site were 194.3 ± 25.2, 14.5 ± 5.1 and 13.3 ± 5.9 Bq kg -1 for 40 K, 238 U and 232 Th, respectively. The effective dose to which the miners are exposed according to exposure scenarios were calculated as 89.9 µSv y -1 for digging and handling of soil and mineral samples in the pit and 63.6 µSv y -1 for handling of soil and mineral

A study of background radioactivity level for Tekirdag, Turkey

The level of background radiation for Tekirdag province of north-western Turkey was assessed in this study. Radon concentrations in indoor air were determined using CR-39 nuclear track detectors and the average (222)Rn activity was found to be 86 Bq m(-3) (equivalent to an annual effective dose of 2.2 mSv). Measurements of gamma doses in air were performed using plastic scintillators and the average absorbed gamma dose rates for indoor and outdoor were found to be 5.7 and 5 microR h(-1), respectively, corresponding to an annual effective dose of 300 microSv. The radionuclide activity concentrations in soil samples collected from the study area were measured through gamma-ray spectrometry and the average activities were determined as 29, 39 and 580 Bq kg(-1) for the natural radionuclides (238)U, (232)Th and (40)K, respectively, and 5.2 Bq kg(-1) for the fission product (137)Cs. The natural radioactivity sources resulted in an annual effective dose of 75 microSv. The radioactivity levels of drinking water samples were measured as 0.044 and 0.1 Bq l(-1) for gross alpha and gross beta activities using a low-background counting technique (equivalent to an annual effective dose of 9 microSv). The results of this study showed that the region's background radioactivity level is in agreement with most Turkish cities.

A study of background radioactivity level for Canakkale, Turkey

This study assesses the level of background radiation for Canakkale province of northwestern Turkey. Radon concentrations in indoor air were determined using CR-39 nuclear track detectors and (222)Rn activity was found to be 167 Bq m( - 3) (equivalent to an annual effective dose of 4.2 mSv). Measurements of outdoor gamma radiation (of terrestrial and cosmic origin) in air were performed using plastic scintillators, and the average absorbed gamma dose rate was found to be 66.4 nGy h( - 1) (corresponding to an annual effective dose of 81.4 muSv). The radionuclide activity concentrations in soil samples collected from the study area were measured through gamma-ray spectrometry, and the average activities were determined as 94.55, 110.4, and 1,273 Bq kg( - 1) for the natural radionuclides (238)U, (232)Th, and (40)K, respectively, and 19.39 Bq kg( - 1) for the fission product (137)Cs. The natural radioactivity sources resulted in an annual effective dose of 184 muSv. The radioactivity levels of drinking water samples were measured as 0.0599 Bq l( - 1) for gross-alpha activity and 0.0841 Bq l( - 1) for gross-beta activity using a low-background counting technique (equivalent to an annual effective dose of 12.25 muSv). The results of this study show that the activity levels of radon in air, radionuclides in soil, and alpha activities in drinking water are higher compared to the data available for other Turkish cities and the world averages. On the other hand, the outdoor gamma dose rates in air and beta activities in drinking water are within natural limits.