Radionuclides In Soil Samples Research Articles

Radiation doses assessment and radon exhalation rate from the soils of Albyda area, Yemen

This work focuses on evaluating the potential health hazards posed by natural radionuclides in soil samples collected from 20 different sites in the Albyda area, Yemen. The activity concentrations of 226Ra, 232Th and 40K and radon exhalation rates in the soil samples were investigated. Alpha GUARD detector was used to estimate 222Rn concentration, while activity levels for natural radionuclides were measured by HPGe detector. The average values obtained for 226Ra, 232Th, and 40K were 27.60 ± 2.40 Bq/kg, 35.07 ± 2.45 Bq/kg, and 544.71 ± 48 Bq/kg, respectively, and for 222Rn concentrations were 135 ± 15 Bq/m3. Our findings show that the concentrations of radionuclides were within the limits of the world average established by UNSCEAR, except the concentrations of 40K, which was slightly higher than the world average (420 Bq/kg), while the average 222Rn concentration was lower than the ICRP reference level of 300 Bq/m3, and the average area exhalation rate 3.46 × 10−5 Bq m−2 s−1 was lower than the UNSCEAR world average of 0.016 Bq m−2 s−1. Therefore, the soil in this study does not pose any radiological hazard to the population due to the harmful effects of ionizing radiation. The results of the current study highlight the potential health hazard posed by radon and radioactivity levels in the soil samples from Albyda area, Yemen, which will help to increase awareness of the radiological hazard and the data could also be used as a reference for future research on radioactivity mapping in the study area.

Assessment of Radionuclides Contents in Soil and Food Samples Due to Civil War in Enugu State, South-Eastern, Nigeria and Its Radiological Hazards

Human activities may influence the distribution of naturally occurring radioactive materials in the environment. This therefore, cause for concern radiological, as human are exposed to these radioactive materials without their consent. This study hereby evaluate the radionuclide contents from natural and artificially occurring radionuclides in soil samples and farm produce in Enugu. Gamma-ray spectroscopy was used to determine the radioactivity concentration level of the environmental radionuclides such as 238U, 232Th, and 40K and manmade radionuclides in soil, cassava, and bitter leaf samples within studied locations in Enugu State, Nigeria. The mean activity concentration of the radionuclides detected in the samples were 1136.74±27.07, 1118.53±4.85, 196.104±0.02 Bqkg-1 for 40K, 41.66±0.04, 22.99±0.38, Bqkg-1 for 238U and 36.44±0.04, 15.89±0.07, 7.69±0.02 Bqkg-1for 232Th. 137Cs ranged from 3.07 ± 0.01 – 7.81 ± 0.03 Bqkg-1. The radioactivity levels and estimated radiological indices were higher than the recommended limits. The values confirmed the reports of different fora on the radiological hazards due to exposure to high radiation in the region assayed.

Assessment of Naturally Occurring Radionuclide in Soil Samples from Kutayi Mining Sites in Muya Local Government Area, Niger State, Nigeria

This work examines the Kutayi mining sites with a view of assessing the activity concentration and effective dose rate of NORM (i.e. 40K, 232Th and 226Ra) in these site absorbed in 8 soil samples collected from different areas within the Kutayi mining sites, A γ-ray spectrometry NaI (Tl) at CERT. ABU Zaria, was used to carry out the analysis of the soil samples. The result shows that, activity concentration for 40K ranged from 428.9269 to 93.6236 BqKg-1; for 226Ra it ranged from 50.1738 to 13.7891 BqKg-1 and for 232Th the ranged is from 52.1095 to 18.7457 Bq.Kg-1, the absorbed dose for 40K ranged from 17.8863 to 3.9041 ŋGy.h-1, for 226Ra the range is from 23.1803 to 3.1614 ŋGy.h-1 and for 232Th range from 31.47419 to 11.3224 ŋGy.h-1. The total mean absorbed dose rate is 42.5341 ŋGy.h-1 and the annual effective dose range from 0.0355 mSvy-1 (i.e. 36 – 76 μSv.y-1), with an mean annual effective dose of 0.0522 mSv.y-1 (i.e. 52.2 μSv.y-1, Also the mean Radium Equivalents (Raeq) obtained ranged from 64.0280 BqKg-1 (KT6) to 135.3245 BqKg-1 (KT8). This results show that, the Raeq is 370 BqKg-1 which is the requirement for soil to be used for dwellings; hence the soil from this site is suitable use for buildings. The mean Hext ranged from 0.1730 Bqkg-1 (KT6) to 0.3438 Bqkg-1 (KT8). The maximum allowed value of (Hext = 1) corresponds to the upper limit of Raeq (370 BqKg-1) in order to limit the external gamma radiation dose from the soil to 1.5 mGy y-1, i.e. index should Hext = 1. All these values for Iα are below the maximum permissible value of Iα= 1 which corresponds to 200 Bq.Kg-1. Hence no radiological hazard is envisaged to dwellers of the study areas and the miners working on those sites.

Assessment of natural radioactivity in soil samples along the coastal villages of Tirunelveli District, Tamilnadu, India using gamma-ray spectroscopy

ABSTRACT Natural radioactivity due to 238U, 232Th, and 40K in soil samples collected from coastal villages of Tirunelveli district, Tamilnadu was measured using a gamma-ray spectrometer. The activity concentrations of radionuclides in soil samples varied in the range of 5.45 to 263.30 Bq/kg for 238U, 72.56 to 1244.26 Bq/kg for 232Th, and 352.82 to 1751.41 Bq/kg for 40K respectively. The mean value of the radiological parameters like radium equivalent activity (549 Bq/kg), the annual effective dose rate indoor and outdoor (1.20 mSvy-1 and 0.30 mSvy-1), external and internal hazard indices (1.50 and 1.74) were estimated. All the radiological parameters exceed the world average values.

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.

Diffusion capability of Cs-137 in compacted soil and bentonite under groundwater-saturated condition

Several researches have been studied the diffusion coefficient (Da) of radionuclide in soil samples in varies location around the world; however, the effect of cations in groundwater as a medium of saturation for Cs-137 diffusion in soil and bentonite remains to be accomplished. Compacted soil and bentonite layers are utilized in the construction of radioactive waste disposal sites, which serve to prevent the release of Cs-137 from the repository to the unsaturated zone. The samples used were soil from the prospective disposal site in SP4—Serpong Nuclear Center (SNC) and bentonite taken from Santrijaya, Tasikmalaya. The diffusion coefficient (Da) is used as indicator of Cesium-137 diffusion in the samples. Experimental measurements were conducted on a diffusion column unit that varied in diffusion time and density conditions to determine diffusion coefficients. The samples were cut into slices and analyzed using Multichannel Analyzer (MCA) unit to measure Cs-137 radioactivity. The measurement results were then incorporated into Fick's Law equation to obtain the value of the diffusion coefficient (Da) of Cs-137 in soil and bentonite. The experimental results showed that the diffusion coefficients of samples with groundwater simulation are in the range of 10–12 m2 s−1 for the local soil and bentonite samples, respectively. Compare to the similar experiment that was conducted previously, the results indicated that the groundwater content could slightly impact the increase in the diffusion coefficient value of Cs-137.

Evaluation of Radioactivity Levels in Soil Samples from Assosa City in Benishangul Gumuz Region, Ethiopia

The specific activity concentrations of naturally occurring radionuclides in soil samples collected from suburban areas of Assosa City was measured using a High purity Germanium (HPGe) detector. The average specific activity concentrations of 238U and 232Th exceed the recommended safe value of 35.0 and 30.0 Bq kg−1, respectively. For 40K, the average activity concentration is below the recommended safe value of 400.0 Bq kg−1. The calculated mean value of the absorbed dose rate is 72.8 ± 3.72 nGy h−1 which exceed the recommended safe value of 59 nGy h−1. The calculated mean annual effective dose equivalent values for indoor and outdoor are 2.11 ± 0.1 mSv y−1 and 0.52 ± 0.02 mSv y−1, respectively. The calculated mean values of the internal hazard index, external hazard index, and gamma index are 0.43 ± 0.013, 0.56 ± 0.01, and 0.5 ± 0.01, respectively, and those values are below the recommended safe value of one. The mean value of excessive lifetime cancer risk is above the threshold value of 0.29 × 10−3. From this study, it is recommended that Assosa soil needs further investigations.

Assessment of radionuclide concentration and associated risks in soils from Iperindo mining sites, Nigeria

The assessment of natural radionuclides in soil samples from artisanal gold mine sites in Iperindo, Nigeria was conducted using different analysis methods. Soil samples collected across three locations and within a control area were analyzed using well-calibrated gamma spectroscopy fitted with a sodium iodide detector. The average activity concentrations (ranges) of 238U, 232Th, and 40 K were found to be 61.55 ± 13.97 (33.40–87.00) Bqkg−1, 72.65 ± 16.83 (41.90–105.10) Bqkg−1, and 1134.99 ± 142.24 (720.50–1722.10) Bqkg−1, respectively for the mining areas and 15.26 ± 6.96 (10.90–20.10) Bqkg−1, 21.46 ± 9.35 (17.40–25.30) Bqkg−1, and 381.04 ± 51.27 (280.30–511.70) Bqkg−1, respectively for the control locations. The average activity concentrations of the radionuclides assessed were above the worldwide permissible limits for the Iperindo mining areas and below the worldwide average for the control areas. The investigation also assessed various radiological parameters, encompassing the radium equivalent, dose rate, annual effective dose rate, internal and external hazard indices, alpha and gamma indices, annual gonadal equivalent, and excess lifetime cancer risk. The recorded values for mine locations were 252.83 Bqkg−1, 119.98 nGyh−1, 0.15 mSvy−1, 0.85 Bqkg−1, 0.68 Bqkg−1, 0.31 Bqkg−1, 1.89 Bqkg−1, 850.23 μSvy−1, and 0.52 ×\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$\ imes$$\\end{document} 10−3, respectively. Except for the radium equivalent, external and internal hazard risks, and the alpha index, which were notably below the recommended threshold, all the other radiological parameters exceeded the globally advised limits. All the radiological parameters from the control areas were below the worldwide average values.

РАДИОЭКОЛОГИЧЕСКАЯ ОБСТАНОВКА В РАЙОНЕ ПЛОЩАДКИ УРАНОВОГО НАСЛЕДИЯ – ШАХТА «СТЕПНАЯ» (КАЛМЫКИЯ)

Purpose: To study the radio-ecological situation on the “uranium legacy” site of the former Stepnaya mine in the Republic of Kalmykia. Material and methods: To measure the ambient dose equivalent rate (ADER), the pedestrian gamma survey method was used using a portable spectrometric complex MKC-01A Multirad-M and dosimeter-radiometer MKC-AT6101c. The activity of gamma-emitting radionuclides in soil samples was measured using a stationary gamma spectrometer from CANBERRA. The activities of 210Po and 210Pb were measured using a radiometric installation UMF-2000 following their radiochemical separation from samples. Short-term measurements of activity concentration (AC) and equivalent equilibrium activity concentration (EEAC) of radon were carried out with an aerosol alpha radiometer for radon and thoron RAA-20P2 Poisk. Doses of radiation exposure to biological objects were estimated using dose coefficients provided by ICRP Publication 136 taking into account recommendations R52.18.820-2015. Results: Gamma ADER values at the mine site vary over the range from 0.1 to 0.36 µSv/h, and on 80 % of the area these values do not exceed the background value of 0.14 µSv/h. Along the road from the mine to Narta village the ADER values do not exceed background values with exception of the area around the dam, where in a local part of this area of about 300 m2 these values reach 0.49 µSv/h. The specific activities of natural radionuclides in the soil are below the criteria for classification as solid radioactive waste (SRW). Under the certain weather conditions, radon EEAC inside the buildings on the site reaches 13 kBq/m3, and on the territory 1-1.5 kBq/m3. Ecological risk for the terrestrial biological objects under consideration (grass, soil worm, snake and mouse-like rodents) does not exceed 0.025. Conclusions: The radiation situation at the Stepnaya mine site meets the requirements of SP LKP-91, which were in force until 2020. However, in order to transfer the facility to a local government body, reclamation work should be carried out in accordance with the Federal Law “On the Transfer of Lands or Land Plots from One Category to Another” dated December 21, 2004 No. 172-FZ and GOST R 59057— 2020 «Environmental Protection. Lands. General Requirements for Reclamation of Affected Lands». Doses of exposure to biological objects do not impact significantly on morbidity, reproduction and life expectancy of terrestrial biological objects.

Studies on radionuclides in soil samples of of Tiruvannamalai District Tamilnadu, India using Gamma Ray Spectrometry

The activity concentrations of natural radionuclides 226Ra, 232Th, and 40K in soil samples from Tiruvannamalai district, Tamil Nadu, have been estimated using NaI (TI) detector-based gamma spectrometry. The mean activity concentration of 232Th in soil samples is greater and poorer for 226Ra and 40K, respectively, when compared with world average values. Radiation hazard estimation was done by the assessment of radiological parameters such as radium equivalent activity (Raeq), absorbed gamma dose rate (DR), annual effective dose rate (HR), and excess lifetime cancer risk (ELCR). These parameters were compared with international criteria. The findings in the soil showed that there is no major radiological risk to the general public by using these soil samples from the Tiruvannamalai district.

Evaluation of Natural Radioactivity Level in Surface Soil from Bambasi District in Benishangul Gumuz Region, Ethiopia.

The study assessed the concentration of natural radionuclides in soil samples from the Bambasi district in Ethiopia's Benishangul Gumuz region using a gamma-ray spectrometer equipped with a high-purity germanium (HPGe) detector. The measured activity concentrations of 238U, 232Th, and 40K in soil samples varied from 46.2 ± 2.25 to 88.49 ± 5.73 Bq/kg, 73.4 ± 4.12 to 119.65 ± 8.45 Bq/kg, and 176.78 ± 8.63 to 396.71 ± 25.39 Bq/kg, respectively. The average concentration of 238U and 232Th exceeded the recommended worldwide population weighted average values of 32.0 and 45.0 Bq/kg, respectively, while the average concentration of 40K was below the recommended value of 420.0 Bq/kg. The mean absorbed dose rate was calculated to be 91.6 ± 5.1 nGy/h, which is above the recommended safe value of 59 nGy/h. The average annual effective dose equivalents for indoor and outdoor exposure were determined to be 2.65 ± 0.14 mSv/y and 0.66 ± 0.1 mSv/y, respectively. The calculated mean values of the internal hazard index, external hazard index, and gamma index across all soil samples were 0.72 ± 0.05, 0.55 ± 0.02, and 0.72 ± 0.02, respectively, all below the recommended safe threshold of one. These findings suggest that the activity concentrations observed in the soil samples exceed safe levels, indicating the necessity for further investigation into radioactivity levels and epidemiological studies regarding potential hazards from high background radiation.

Spatial distribution of 137Cs; 40K, 226Ra, 232Th in soils of Monchegorsk city (Murmansk region)

The purpose of the study was to establish the patterns of spatial distribution of radioactivity of technogenic 137Cs and natural radionuclides 232Th, 226Ra, 40K in urban soils of Monchegorsk. Location and time of the study. Soil samples, were collected in summer 2018 in the Monchegorsk city, Murmansk region, Russia. To study the specific activity of radiocesium and natural radionuclides, soil samples were taken from topsoil (0-5 cm) at 82 sites, including 68 sites within the city territory (urban soils) and 14 sites beyond the city limits in the subtorch areas strongly affected by the Severonickel factory. Similar studies of urban soils in Monchegorsk had not been carried out previously. Methods. During expeditionary work and laboratory research, soil, radiological, and mathematical and statistical methods were used. When carrying out gamma spectrometric measurements, radionuclides 137Cs, 226Ra, 232Th and 40K were determined on a low-background semiconductor gamma spectrometer ORTEC (USA) based on a high-purity coaxial germanium detector GEM10P4–70 (HPGe) with a SBS-75 pulse signal processor and Gamma-software. The resolution of the gamma spectrometer along the 1.33 MeV line (60Co) was 1.75 keV, and the relative efficiency was 15%. Calibration and quality control of gamma spectrometric measurements was carried out using volumetric activity measurements with 1-L Marinelli vessels of different densities (RITVERZ, Russia-Germany). Main results. The values of specific activity of radionuclides in soil samples were as following: in the technogenic 137Cs up to 31.3 Bq/kg and in the subtorch soils up to 63.4 Bq/kg. Specific activity of natural radionuclides in urban soils reached to 14.2 Bq/kg for 226Ra, whereas in the subtorch soils it reached 21.6 Bq/kg. The specific activity of 232Th in urban soils reached 18.3 Bq/kg, with 17 Bq/kg registered for the subtorch soils. As for 40K, its specific activity reached 498 Bq/kg in the urban soils and 317 Bq/kg. Conclusion. The gamma survey of the Monchegorsk territory did not reveal any anomaly in radiation. The dose rate of gamma radiation in the city does not exceed 0.074 μSv/hour, which is less than the values elsewhere in Russia, ranging from 0.04 to 0.20 μSv/hour. The obtained data about specific activity of technogenic 137Cs and natural radionuclides 232Th, 226Ra, 40K in the Monchegorsk soils are typical for the Murmansk region.

Assessment of Radiation Hazard Indices Due to Natural Radionuclides in Soil Samples from Imo State University, Owerri, Nigeria.

A total of 30 soil samples from different sampling points at Imo State University (IMSU), Owerri, Nigeria were collected for the study. The activity concentrations of naturally occurring radionuclides (238U, 232Th, and 40K) were measured in the samples by gamma-ray spectrometry using NaI (TI) detector. Absorbed dose rate (D), annual effective dose (AED), radium equivalent activity (Raeq), and radiological hazard index parameters (activity utilization index [AUI], external hazard index [Hex], internal hazard index [Hin], and excess lifetime cancer risk [ELCR]) due to the naturally occurring radionuclides were determined. The mean activity of 238U, 232Th, and 40K were found to be 20.32 ± 3.22, 22.55 ± 0.68, and 91.63 ± 1.54 Bqkg-1 which were lower than the world average reference mean values of 33, 45, and 420 Bqkg-1for 238U, 232Th, and 40K, respectively, as reported by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The average value of D, Raeq, AUI, ELCR, Hex, and Hin in the soil samples was 26.86 ± 1.97 nGyh-1, 59.62 ± 4.14 Bqkg-1, 0.42 ± 0.03, 0.14 ± 0.01 (×10-3), 0.16 ± 0.01, and 0.22 ± 0.02, respectively. The annual effective dose to the general public was 33.07 ± 2.40 μSvy-1. This value lies well below the average worldwide reference value of 0.7 mSvy-1, as reported by UNSCEAR. Soil samples from IMSU pose no significant radiological health hazards to the university community.

Natural and Artificial Radioactivity Concentrations and Health Risks due to Radionuclides in the Soil of Nevşehir (Cappadocia)

Natural and artificial radionuclides in the surface soil samples collected from the Nevşehir (Cappadocia) region were analyzed using gamma spectrometry employing an HPGe detector. Activity concentrations of 226Ra, 232Th, and 40K range from 58.31 to 77.40 Bq kg−1, 60.56 to 90.97 Bq kg-1, and 796.42 to 1142.8 Bq kg-1, respectively. The values indicate that the activity concentrations of the natural radionuclides in the soil samples were higher than the world average. Since Turkey is a country greatly affected by the Chernobyl accident, 137Cs activity concentration was measured to determine whether its effect continues. The activity concentration of 137Cs ranges from Minimum Detectable Activity (MDA) to 6.88 Bq kg−1. In addition, the radium equivalent activity, the absorbed dose rate, the annual effective dose equivalent, and the excess lifetime cancer risk parameters were calculated to determine the radiological effect of natural and artificial radionuclides on the population in the study area. All values except the radium equivalent activity were found to be above the world average.

Evaluation of natural radioactivity in the soil surrounding Bhabha Atomic Research Centre, Visakhapatnam, Andhra Pradesh, India

Abstract Activity concentrations of naturally occurring radionuclides in soil samples collected during 2013–2018 from different 53 locations around Bhabha Atomic Research Centre (BARC), Visakhapatnam, Andhra Pradesh, India, were determined using high-purity germanium gamma-ray spectrometry. An R and D center of BARC is upcoming at Visakhapatnam, North coastal Andhra Pradesh. The annual effective dose (AED) and the radiation indices from the soil activity were evaluated to generate the baseline data for this area. The average activity concentrations of the naturally occurring radionuclides 238U, 226Ra, 232Th, and 40K in the soil samples studied are 29 ± 8 Bq/kg, 31 ± 1 Bq/kg, 188 ± 2 Bq/kg, and 471 ± 10 Bq/kg, respectively. The concentration of 226Ra and 40K in the collected samples is comparable with the world average concentrations of 33 Bq/kg and 420 Bq/kg, however, 232Th is observed to be higher than the world average of 45 Bq/kg. AED due to external terrestrial radiation from the region studied is in the range the range 0.37 to 2.5 mSv/y with an average of 0.9 mSv/y. The mean radium equivalent activity values for around 70% of the studied samples are lower than the permitted levels of 370 Bq/kg. The mean external exposure index has been determined to be around the safe criterion limit of unity. The mean value of the representative level index Iϒ is 2.4. Higher values in some locations are due to thorium in monazite deposits. This report will be useful as preoperational study to evaluate the impact on the environment due to ongoing and future man-made developments.

ASSESSMENT OF NATURAL RADIONUCLIDES IN SOIL SAMPLES FROM MICHIKA, ADAMAWA, STATE NIGERIA

Naturally occurring radionuclides in the environment constitute about 85% of public exposure to terrestrial gamma radiation. These radionuclides can be found in sands,clays, soils and rocks, and many ores and minerals, commodities, recycled residues, and other appliances used by humans. There is therefore the need to assess the occurrence of natural radionuclides in Soil Samples from Michika, Adamawa State Nigeria. Forty-six (46) soil samples were collected across different location in Michika, Adamawa State, Nigeria. Gamma ray spectroscopy was used for the analysis. The results obtained show that the mean activity concentration for 226Ra, 232Th and 40K are 81.27, 101.28 and 324.79 Bq/kg respectively. These values are higher than the control value of 35,30 and 35 Bq/kg for 226Ra, 232Th and 40K set by UNSCEAR. The absorbed dose rate (D) ranges from 60.77 to 248.65 nGy/h, which is above the maximum UNSCEAR accepted value of 59nGy/h. The values of total annual effective dose lie between 0.08 and 0.31 mSv y-1 with mean value of 0.14mSv y-1. Also, the mean values of Radium Equivalent Activity were 251.11 Bq/kg. Almost all the value of Raeq were below the maximum recommended value. The mean value of total cancer risk range from 3.28E-6 to 1.3E-5 with mean value of 5.93E-6. All the mean values were above the acceptable range. It can be concluded that the soil is radiologically unsafe for human and animal use. Continuous radiological monitoring of the soil is recommended to safeguard the health of the populace.

Assessment of the Natural Radioactivity Levels of Soil Samples in IT1 Oil Reservoirs in Kirkuk City, Northeast Iraq

In this study, gamma-ray spectrometry with an HPGe detector was used to measure the specific activity concentrations of 226Ra, 232Th, and 40K in soil samples collected from IT1 oil reservoirs in Kirkuk city, northeast Iraq. The “spectral line Gp” gamma analysis software package was used to analyze the spectral data. 226Ra specific activity varies from 9 0.34 Bq.kg-1 to 17 0.47 Bq.kg-1. 232Th specific activity varies from 6.2 0.08 Bq.kg-1 to 18 0.2 Bq.kg-1. 40K specific activity varies from 25 0.19 Bq.kg-1 to 118 0.41 Bq.kg-1. The radiological hazard due to the radiation emitted from natural radionuclides in soil samples was also assessed. The average values of the radium equivalent (Raeq), external hazard index (Hex), internal hazard index (Hin), gamma index (I), absorbed dose rate (D), outdoor (AEDEout) and indoor (AEDEin) annual effective dose equivalent were 35.391 Bq.kg-1, 0.095, 0.128, 0.253, 16.118 nGy.h-1, 0.0197 mSv.y-1, and 0.0790 mSv.y-1, respectively. All values obtained for the activity concentrations for 226Ra, 232Th, and 40K and the radiological hazard were lower than the global values. This indicates that no harmful radiation effects are posed to the population who work and live near the study area.

РАСПРОСТРАНЕНИЕ УГЛЕРОДА-14 В ОКРУЖАЮЩЕЙ СРЕДЕ ПРИ НОРМАЛЬНЫХ УСЛОВИЯХ ЭКСПЛУАТАЦИИ КУРСКОЙ АЭС

Introduction: 14C is one of the fifteen radionuclides that account for at least 99 % of the radiation dose to the critical group of the population from NPP emission sources. The continuous growth of the total capacity of operating NPPs leads to a significant increase in the amount of 14С emitted into the environment during NPP operation. Efficient capture and disposal of 14C, which has a half-life of 5760 years, is a very laborious undertaking. At the same time, due to the high mobility of this radionuclide, local foci of contamination with 14C can appear both near the NPP at a distance of 1–2 km from its ventilation pipe, and in soil and plants located at a distance of 20–30 km from the NPP due to the transfer of air masses. Therefore, the control of the formation of 14C during the operation of nuclear power plants, its content in emissions and discharges of nuclear power plants, as well as distribution in the environment is an urgent problem today. Purpose: Analysis of the environmental pollution due to emissions and discharges of radiocarbon from the Kurskaya nuclear power plant. Material and methods: During the research, a method being developed by specialists of the Laboratory for Radiation Safety of Personnel was used to determine the specific activity of 14C in soil and vegetation. To explore the 14C content in the air, the method of bubbling air through a TASC-HT-HTO-C-14 flow meter-sampler (Overhoff technology, USA) and the method of air conditioning through a Ballu BDH-15L air dryer (Ballu, Russia) were used. To prepare counting samples from selected soil and food samples, a method based on the combustion of selected samples in a Pyrolyser-6 Trio catalytic decomposition system was used. All prepared counting samples, including samples from surface water and biosubstrate of the personnel of the Kursk NPP and the population, were measured by liquid scintillation spectrometry on a Tri-Carb 3180 TR/SL alpha, beta spectrometer. Results: On the basis of an integrated approach to assessing the content of 14C in air, water, soil and food, an analysis of the formation of environmental pollution due to emissions and discharges 14C from the Kurskaya NPP was carried out. Conclusions: An increased content of the 14C radionuclide in soil samples, food products and vegetation in the area of the Kursk NPP with RBMK-1000 nuclear reactors is shown, both in comparison with the content of natural 14C and NPPs operating BN-600,800 and VVER-1000 nuclear reactors. The necessity of taking into account radiocarbon emissions from NPPs into the environment in the problem of optimizing the radiation protection of the population under the conditions of normal operation of NPPs is confirmed.

Investigation of radioactivity level in drinking water resources and soil samples collected from the Hawraman villages, Iraq

In the present study, the RAD7 and NaI(Tl) techniques were utilized to determine the radon concentrations in drinking water resources and the natural primordial radionuclides in soil samples collected from Hawraman villages. The measured radon concentrations ranged from 1.7 ± 0.6 to 34.0 ± 2.8 Bq L−1 with an arithmetic mean of 14.8 ± 1.2 Bq L−1. This research demonstrates that roughly 54% of drinking water samples exceed the EPA-recommended level of 11.1 Bq L−1. For adults, children, and infants, the total annual effective doses for the three types (Ding, Dinh, and Ddi) vary from 7.6 to 149.2 μSv y−1 with an average of 65.0 μSv y−1, 8.1–160.0 μSv y−1 with an average of 69.7 μSv y−1, and 10.5–207.0 μSv y−1 with an average of 90.2 μSv y−1.18.2%, 22.7%, and 36.4%, respectively, of the annual effective dose for adults, children, and infants exceeds the 100 μSv y−1 level recommended by WHO and UNCEAR 2000.The activity concentrations of 226Ra, 232Th, and 4 K in soil samples varied from 10.9 ± 0.1 to 32.6 ± 0.2 Bq kg−1, 18.3 ± 0.4 to 52.1 ± 0.6 Bq kg−1, and 252.7 ± 2.5 to 585.6 ± 3.7 Bq kg−1. The arithmetic mean concentrations of 226Ra, 232Th, and 4 K were determined to be 19.4 ± 0.2 Bq kg−1, 36.2 ± 0.5 Bq kg−1and 426.6 ± 3.2 Bq kg−1, respectively.This research reveals that the average soil activity concentrations of 226Ra, 232Th, and 4 K are within the global average limits of 32, 45, and 420 Bq kg−1, respectively. Comparing the concentrations to global averages, some soil samples revealed significant amounts of radionuclides, with around 18% of 232Th and 41% of 4 K. The computed radiological hazard indices of 100% of Raeq., 82% of Dout, 82% of Eout, and 95.5% of ELCRout are all below the internationally recommended levels declared by Unscear 2000.

Determination and Distribution Map for Radionuclides in Soil Samples from Different Location by Gamma Spectrometry Using Software Analysis

The fundamental goal of the current study is to determine the mean activity concentrations of natural and artificial radionuclides of 226 Ra, 232 Th, 40 K, and 137 Cs using gamma spectrometry for three locations, in Egypt, Saudi Arabia, and Iraq, which are significant and vital countries in the Middle East. The mean absorbed dose rate equals 22.35, 28.96, and 43.34 nGy h -1 for Egypt, Saudi Arabia, and Iraq. The results are consistent with international reports. The dose contribution percentages for investigated locations are 24 %, 30 %, and 46 % for Egypt, Saudi Arabia, and Iraq, respectively. The obtained results were clarified by statistical measurements using one-way ANOVA test to determine the distribution and differences between the averages of the three groups under study, as they may be influenced by geological variations and human intervention . It was found that the Iraq samples followed a symmetrical, standard normal distribution, while samples from Egypt and Saudi Arabia did not. Statistically significant differences were found between the data from the three countries.