Quantifying Radon-222 (222Rn), gross alpha (α) and beta (β) emitting radionuclides in drinking water is crucial for assessing water quality and potential long-term impacts on human health. Therefore, the aim of this study is to investigate the radiological characteristics and the spatial distribution of drinking water samples from Diyarbakır province, Türkiye using the geostatistical approach. The measurements of 222Rn and gross α/β were scrutinized using a radon gas analyzer (AlphaGUARD PQ 2000 PRO) and a gas proportionate α/β counter (Berthold, LB 770 model). Spatial distribution maps were generated through the Ordinary Kriging method to visualize these parameters. The values of 222Rn, gross α and β activity in drinking water were established to be in the range of 258-1393 mBq L-1, 12-243 mBq L-1 and 32-380 mBq L-1, respectively. The associated averages of the total annual effective dose (AEDtotal) and total lifetime cancer risk (LCRtotal), of drinking water were estimated to be 59.56 μSv y-1 and 2.57E - 04, respectively. Although the average LCRtotal was below the WHO threshold (3.85E - 04), it remained above the United States Environmental Protection Agency (US EPA) limit (1E - 04). These outcomes highlight the need for ongoing monitoring and further investigation of local water supplies to safeguard public health.
The research aimed to evaluate the radiological quality of drinking water in Şırnak city, Türkiye. A gas proportional α/β counter (Berthold, LB 770 model) was employed to quantify the gross α and β activities in a total of seven drinking water samples. The findings revealed that the average gross α and β activities were 27 mBq/L (range: 19-35 mBq/L) and 117 mBq/L (range: 24-534 mBq/L), respectively. The age-dependent annual effective dose (AED) resulting from the ingestion of drinking water in Şırnak was meticulously estimated. The calculated average total AED values (alpha+beta) were 9.5 μSv/y for infants, 22.1 μSv/y for children, and 46.2 μSv/y for adults. The average lifetime risk of radiation-induced cancer (LTR) for the population was found to be 1.7×10⁻⁴. Overall, the study concluded that the radiological parameters in Şırnak city's drinking water were within the permissible limits recommended by the World Health Organization (WHO). These findings provide significant assurance that the drinking water in the region is safe for consumption, concerning radiation exposure. Furthermore, the results imply that existing water treatment and monitoring systems are effective in maintaining radiation levels within safe limits. The study highlights the importance of regular testing and evaluation of water quality to protect public health.
In this study, the spatial distribution model has been aimed to characterize the radiometric parameters in drinking water and soil samples of Siirt City in Turkiye using the geostatistical method. The gross & alpha; and & beta; measurements in the water samples and radiometric measurements in the soil samples were performed using a gas proportional & alpha;/& beta; counter (Berthold, LB 770 model) and a gamma spectroscopy system (HPGe-detector), respectively. The spatial distribution maps, covering the whole region using the ordinary kriging method, were created visually. The gross & alpha; and & beta; activities in the water samples varied from 9 to 40 and from 21 to 252 mBq L-1. The corresponding arithmetic average of the annual effective dose of gross & alpha; and & beta; of drinking water was estimated to be 5.3 and 52.3 & mu;Sv y(-1), respectively. In soil samples, the arithmetic average values of U-238, Th-232, K-40, and Cs-137 radionuclides were 17 & PLUSMN; 6, 20 & PLUSMN; 7, 445 & PLUSMN; 166, and 4 & PLUSMN; 6 Bq kg(-1), respectively. The arithmetic average absorbed dose rate (D), annual effective dose (AED), and excess lifetime cancer risk (ELCR) values in soil samples were calculated as 38 nGy h(-1), 0.05 mSv y(-1), and 0.165 x 10(-3), respectively, for soil samples. The radiometric parameters of the sample were lower than those of the guideline levels recommended in the literature. Furthermore, the interpolation maps were evaluated in terms of the soil structure of the region.
In this study, the performance of the Sequential Gaussian Simulation (SGS) approach was studied with the aim of accurately determining local health risk distributions associated with trace elements (V, Cr, Mn, Co, Ni, Cu, Zn, As, and Pb). This study plays a crucial role in determining the distribution of health risk levels, especially from heavy metals. In the SGS approach, health risk levels (non-carcinogenic and carcinogenic) were calculated for pixel sizes of 250 × 250 m2. Results were compared to the conventional Ordinary Kriging (OK) method. The cross-validation performances of both methods were compared. Non-carcinogenic health risks calculated according to SGS and OK for children were, respectively, ρc: 0.57 and 0.23, RMSE: 0.45 and 0.57, and MAE: 0.33 and 0.43. In the case of adults, non-carcinogenic SGS and OK results were, respectively, ρc: 0.53 and 0.24, RMSE: 0.06 and 0.07, and MAE: 0.04 and 0.05 for adults. Carcinogenic health risk estimates obtained by SGS and OK were, respectively, ρc: 0.72 and 0.31, RMSE: 4.1 × 10−5 and 5.8 × 10−5, and MAE: 3.2 × 10−5 and 4.3 × 10−5 in the case of children, and in the case of adults the results were, respectively, ρc: 0.71 and 0.30, RMSE: 5 × 10−6 and 4.3 × 10−6, and MAE: 4 × 10−6 and 5 × 10−6. These results indicated that SGS offered a more accurate approach in determining health risk distributions.
In this study, the activity concentrations of gross alpha and gross beta in 125 drinking water samples (16 tap and 109 spring waters) collected from Ankara province were measured using a gas proportional alpha/beta counter. The average (range) activity concentrations of gross alpha and gross beta were determined as 105 (20-495) mBqL(-1) and 195 (70-850) mBqL(-1), respectively. Average annual effective dose to adults caused by ingestion of water samples was estimated as 74.1 +/- 43.2 mu Sv y(-1). The average estimated cancer risk value depending on irradiations was calculated as 3.8 x 10(-4) and 2.6 x 10(-4) for the region using the nominal probability coefficients recommended by ICRP 60 and ICRP 103, respectively. Annual effective dose values in 10.4% of samples exceeded the limit values suggested by WHO for drinking waters in terms of beta activity and this was 0.8% for alpha activity. Moreover, contribution of K-40 to the gross beta activity in drinking waters of the region was determined as 47%.
Trace elements measured in Artvin province soil samples in Northeast Turkey were assessed using pollution and health indices. The study area is positioned in one of the essential metallogenic belts in Turkey. This attempt is the first endeavor toward the study area in this context. The measured trace elements are As, Co, Cr, Cu, Mn, Ni, Pb and Zn, as they were assessed using pollution indices, enrichment factor, geo-accumulation index, contamination factor, and health risk assessment methods. According to the results of enrichment factor (EF), geo-accumulation index (Igeo), and contamination factor (CF), the soils of Artvin province show a slightly severe enrichment, moderately polluted and very high contaminated with arsenic, respectively. The pollution load index score (PLI) index (1.57) indicates that Artvin province is polluted in terms of trace elements. The hazard index (HI) calculated values for children and adults were 1.55 and 0.18, respectively. This revealed that the aforementioned metals can have non-carcinogenic effects (HI > 1). Total potential carcinogenic health risk (TCR) values for children and adults were 3.22 × 10–5 and 1.40 × 10–5, respectively. The non-carcinogenic risk level indicates that there may be a risk for children rather than adults.
In the present study, the radioactivity levels of water samples collected from the main water supply network in Trabzon province and districts and soil samples taken from the vicinity of the water network were measured. An Alphaguard-PQ2000 radon gas detector was used to determine the seasonal radon gas level in the water samples. An HPGe detector was used to determine the level of radioactivity in soil and water samples. The average concentration of 222Rn in drinking water ranges from 0.56 ± 0.51 to 13.3 ± 5 Bq L-1. In water samples, average gross alpha and gross beta values were measured as 8 ± 1 and 43 ± 1 mBq L-1, respectively. The average concentrations of 238U, 232Th, 137Cs, 40K radionuclides in soil were measured as 51 ± 2, 21 ± 2, 16 ± 1, 28 ± 7 Bq m-3, respectively. The average concentrations of 238U, 232Th, 137Cs, 40K radionuclides in drinking water were measured as 147 ± 5, 25 ± 2, 77 ± 2, 12 ± 2 mBq L-1, respectively. When the radon concentrations for drinking water were examined, it was found that the radon concentration of the three samples was above the limit value (11 Bq L-1) allowed by the US-EPA for drinking water. All other results are below the limit values.
In this paper, an encircling probe design used in the inspection of conductive wires, which are qualified as aluminum clad steel (ACS) wire is made. The eddy current systems are widely used for the quality control of conductive materials as one of non-destructive testing methods. In these systems, it is possible to design and to use different types of probes according to the material type. Internal, encircling and surface probe types are used for the inspection of pipes, wires and plate conductive materials, respectively. The discontinuities on the conductor surfaces are detected and the changes in the inductance values of the coils of probes are analyzed with the electronic hardware and the quality control of the material is ensured. In this study, a sensitive probe design is realized to detect various defect on wire surfaces. The inductance value of the designed probe is calculated by using two and three dimensional finite element analysis (FEA) and the obtained results are compared. The inductance change of the probe was measured by an LCR meter while the probe contained sample ACS wires with different types of defects, these values are given in the table and the change graph is plotted. In addition, an impedance bridge circuit was set up with the probe and the results of the change in voltage induction on the coil are given as an oscilloscope image.
Bu çalışmada, Karadeniz Bölgesinde az sayıdaki jeotermal kaynaktan birisi olan Fatsa İlçesi, Ilıca Köyü sınırları içerisinde bulunan, Sarmaşık Kaplıcası termal tesisinde radon gazı ölçümleri yapılmıştır. Kaplıca havuz ortamı, resepsiyon, restoran olmak üzere üç kısımda hava ortamında Cr-39 ve Alpha GUARD PQ 2000 radon dedektörleri yaz ve kış mevsiminde radon gazı ölçümleri yapılmıştır. Yapılan ölçüm sonucunda elde edilen radon gazı değerleri kullanılarak kaplıca ortamında çalışan personel için yıllık etkin doz eşdeğerleri hesaplanmıştır. Ayrıca kaplıca suyu ve kaplıca tesisi içme suyunda radon gazı ölçümü yapılmıştır. Ölçüm sonuçları uluslararası limit seviyeleri ile karşılaştırılmıştır.
In this study, moss samples which have radiologic indicator characteristic were collected from 80 stations in Artvin to determine the natural (Ra-226, Th-232, and K-40) and artificial (Cs-137) radioactivity levels. Natural and artificial radioactivity results were observed that range activity values for Ra-226, Th-232, K-40 and Cs-137 reach the levels of <1.3 - 31.6 Bq kg(-1), <0.7 - 51.7 Bq kg(-1), 56.3 - 1100 Bq kg(-1) and <0.5 - 535 Bq kg(-1), respectively. Average values of radioactivity results were determined as 6.5 Bq kg(-1), 6.9 Bq kg(-1), 366.9 Bq kg(-1) and 26.8 Bq kg(-1) for Ra-226, Th-232, K-40 and Cs-137, respectively. Pre-determined radiologic levels in the soil samples in the study area were compared with these results. Furthermore, obtained results were evaluated with similar studies in the literature. The estimated values of unmeasured fields to determine the radiologic distribution of the study area were determined with Ordinary Kriging method, and radiologic maps were created for each radionuclide by conducting interpolated value estimation.
The aim of the study is to determine the ambient radiation level in Gumushane province. With this aim, the gamma dose ratios absorbed in the air were surveyed by a portable gamma detector. The activity concentrations of 226Ra, 232Th, 40K, and 137Cs in soil samples have been measured by the gamma spectrometric analysis system. The gross alpha and beta activity concentrations in drinking water were also determined by the alpha and beta counting system. By considering the geological structure, the soil samples have been obtained from 62 different spots. In addition, 77 samples of natural and tap water have been collected from different points of the province. The samples were analyzed at the Cekmece Nuclear Research and Training Center in Turkey. Absorbed gamma dose rates in the air were measured in 338 different points in the studied area.
Background: The aim of this study is to measure the level of radon gas in the thermal springs of the four seasons in the Black Sea Region and to determine the gamma activity levels in the soils around them. Materials and Methods: Indoor radon activity concentrations of four spa facilities, namely Ladik, Havza, Ilicakoy, and Ayder, were measured using CR-39 passive radon dosimeters and active radon monitoring AlphaGUARD for all four seasons. Radon activity concentrations in the soil in the vicinity of these spa facilities were measured using AlphaGUARD. Radionuclides in the soil samples collected from the spa regions were also determined using gamma-ray spectroscopy. Results: The highest radon value in the air environment in the spa facility was measured in swimming pools. Indoor radon levels in the spa's swimming pool vary within a wide range, (30-2118) Bq.m(-3). The average radon gas levels in the soil around the Ayder, Havza, Ladik and Ilicakoy hot springs were measured as 38 +/- 1 kBqm(-3), 9 +/- 1 kBq m(-3), 50 +/- 3 kBqm(-3), 955 +/- 5 kBqm(-3), respectively. Conclusion: The annual effective doses due to indoor radon sources changed from 0.6 mSv to 13.4 mSv for workers, and from 1 x10-4 mSv to 3x10-1 mSv for patients. The annual effective dose equivalents from the soils around the spa were calculated to be between 82-558 mu Sv y-1. The results were compared with those of other measurements performed in different parts of the world.
Water is of vital importance for human life and health. Therefore, drinking water must be safe and quality enough to be consumed by humans. In this study, 19 commercially available Turkish brands of bottled drinking water (BDW) were analyzed to assess the radiological and chemical quality of these waters. The radioactivity concentrations of gross alpha and beta in BDW samples were determined by using a gas proportional alpha/beta counter. The average gross alpha and beta radioactivity concentrations were 21 +/- 5 mBq/L and 59 +/- 12 mBq/L, respectively. The average annual effective radiation doses due to consumption of BDW samples were estimated as 8, 12 and 24 mu Sv/y for infant, children and adult, respectively. The concentrations of anions (fluoride, chloride, bromide, nitrate, nitrite, sulfate and phosphate) and cations (Mg, Sr, Fe, Pb, Hg, Zn, Cr, Co, Ni, Cd and Mn) in BDW samples were determined using an ion chromatography system and inductively coupled plasma optical emission spectrometry, respectively. The average concentrations of fluoride, chloride, nitrate and sulfate were determined as 32.1, 1882.5, 2050.7 and 4776.9 mu g/L, respectively. The average concentrations of Mg, Sr, Fe, Pb, Hg, Zn, Cr, Co, Ni, Cd and Mn were found as 2899.0, 62.9, 3.45, 3.18, 2.0, 2.0, 1.9, 1.7, 1.7, 1.2 and 1.0 mu g/L, respectively. The results reveal that all radiological and chemical values measured in BDW samples, except for Hg, are lower than the limit values set by national regulations and World Health Organization. The average Hg concentration is higher than the limit values set by national regulations.
In this study, indoor and outdoor radon (222Rn) surveys were carried out in the summer and winter seasons in homes of one hundred lung cancer patients in the year 2013–2014. The aim was to investigate the relationship between radon and cancer patients. Lung cancer patients completed a questionnaire concerning their living environment, various physical parameters and living habits. Pearson correlation and t tests revealed no meaningful results between radon concentrations, on one hand, and environmental and personal living habits, on the other hand. Consequently, the BEIR VI model was adapted and 222Rn exposure was estimated to be responsible for about 12% of the lung cancer incidences in the winter season and around 5% in the summer season in the Rize Province. However, due to the limited number of data and numerous parameters that could lead to lung cancer, the estimations done with the model should be taken very lightly. The annual effective doses due to inhalation of indoor and outdoor 222Rn were estimated to be, respectively, 1.43 and 0.94 mSv y−1. The indoor and outdoor annual effective doses were, respectively, close and below the world annual effective dose (1.3 mSv y−1). At the district level, the indoor annual effective dose equivalent in the İyidere district was 4.52 mSv y−1, which was 3.5 times greater than the world average. The number of patients in the majority of the houses in this district was more than one.
The aim of this study was to determine natural radioactive and heavy element concentrations in Mersin drinking water samples before the commissioning of the Akkuyu nuclear power plant and to collect data for possible environmental contaminations in the future. Drinking water samples were taken from the provincial center, districts, and populated villages. The annual effective dose of natural radionuclides and cancer risks were calculated for each person living in the city. Hazard index and cancer risk were calculated, which were caused by heavy elements. Mean gross alpha and beta radioactivity concentrations in drinking water were 0.059 Bq/L and 0.120 Bq/L, respectively. The annual cumulative effective dose for people was 30.83 μSv. Average estimated excess cancer risk related to this exposure was 16.9 × 10−5 . Mean metal concentrations of Cr, Ni, Zn, Cu, Ba, and Cd in drinking water were 1.33, 4.65, 54.8, 11.1, 26.3, and 0.36 μg/L, respectively. Pb and As were lower than the detection limits. Mean calculated hazard index depending on heavy metal concentration was 6.8 × 10−1 for drinking water. Cancer risks of heavy metals decreased in the order of Cd > Cr > Ni for the region.
The purpose of this study is to determine the amount of various trace elements and the concentration of gross alpha and gross beta radioactivity in human teeth and also find out their possible effects on humans. Fifty-six tooth samples were collected from female and male subjects of four different age groups, all of whom reside in Istanbul (0-18, 19-30, 31-45, 45 +). In addition, the variation of trace elements such as Al, Ba, Ca, Cl, F, Fe, K, Mg, Na, P, S, Si, Sr and Zn for the age groups of both genders was examined by trace element analysis. The mean gross alpha and gross beta concentrations were observed in the range of 31.0-47.8 Bq/kg and 71.2-89.2 Bq/kg respectively for the female subjects and 52.7-82.1 Bq/kg and 114.0-154.4 Bq/kg respectively for the male subjects. The radioactivity level was higher in the tooth samples of the male subjects than those of the female subjects. The results, when compared with similar studies, suggest that the concentrations of both gross alpha and gross beta radioactivity in the female subjects were quite smaller than those in the male subjects. Furthermore, it was observed that the concentrations of trace elements were generally the highest in the age groups of 31-45 and 45 +, which are around the time when the body functions in humans start slowing down. The findings of study would be useful for creating a biomonitoring database, which has not yet been done in this area of study.
ABSTRACT Radon (222Rn) measurements were conducted in the Pileki Cave with Radim 3A Active Radon Monitor equipment. Measurements were also done with the passive sampling method with CR-39 nuclear track detectors by exposing them for three months in the cave. Radon concentrations obtained from the active and passive sampling methods showed that, firstly, the concentrations inside the cave measured by the latter method differed greatly due to high humidity levels up to 88%. The total inside radon exposure dose equivalent people were subjected to was estimated to be 19 µSv a−1 for visitors and 24,065 µSv a−1 for guides. The gamma absorbed dose rates were determined for inside and outside the cave. The dose rates were calculated by means of using the 226Ra, 232Th and 40K activity concentrations and by means of real-time measurements. The gamma absorbed dose rates were found to be much higher than the value of 55 nGy h−1 given by UNSCEAR. In addition, the mineralogical compositions and elemental analyses of samples taken from the cave were determined by XRD and WD-XRF methods.
In this study, the radiological characterization of top soil in the Artvin region, the assessment of relevant health risks, and obtaining the distribution of radiological parameters in soil of the region by means of the geostatistical method were aimed. Mean concentration values of 226Ra, 232Th, 40K, and 137Cs radionuclides in 117 soil samples were determined by gamma spectrometric analysis as 42.26, 27.57, 390.42, and 14.87 Bq/kg, respectively. According to the results obtained, the radium equivalent activity (Raeq), the internal radiation hazard (Hin), the external radiation hazard (Hex), and the gamma representative level (Iγr) were found to be 111.75 Bq/kg, 0.41, 0.30, and 0.81, respectively, for the region. In addition, mean absorbed dose rate, annual effective dose equivalent, and excessive lifetime cancer risk values were calculated as 54.79 nGy/h, 0.067 mSv/year, and 0.00023, respectively, for the province. In addition, it was determined that all radiological parameters obtained for the region were lower than the worldwide averages. Finally, in order to estimate the activity for unsampled points and to determine the radiation distribution, the interpolations for each radionuclide were done through ordinary kriging method; the spatial distribution maps were created using these estimations, and it was seen that the distribution of the radionuclides around the region was quite compatible with both the calculated dose rates and cancer risk distribution in the region.