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An investigation was conducted to determine radon concentrations, radon exhalation rate, and potential radiological hazard parameters associated with cement collected from five factories in Sulaymaniyah city, Kurdistan region, Iraq. Using solid-state nuclear track detectors such as CR39, the samples were analyzed by etching processes. The average radon concentration, radium concentration, and radon exhalation rate were 138.16 Bq m - 3 , 0.254 Bq kg - 1 , and 0.317 Bq m - 2 h - 1 , respectively. In sample 14, radon concentrations were within the suggested range of 200–600 Bq m - 3 , and the radon exhalation rate was well below the global average of 57.600 Bq m - 2 h - 1 . In addition, parameters related to potential radiological hazards were calculated for cement samples, the average annual effective dose indoor and outdoor were 3.49 and 1.31 mSv y - 1 , so this study's value was within the global average limitations (1–5 mSv y - 1 ). Also, the excess lifetime cancer risk indoor and outdoor were 12.5 × 10−3 and 4.69 × 10−3 greater than the world value of 0.29 × 10−3. [ABSTRACT FROM AUTHOR]

The study measured the activity concentrations of various radionuclides (238U, 234U, 230Th, 226Ra, 222Rn, 232Th, 40K, and 235U) using γ-ray spectrometry in 11 black shale samples from three trenches and a wall in Budaa area, southwestern Sinai, Egypt. The samples were taken from different parts of Magharet El Meyiah Formation (top, middle, and base) to understand radionuclide migration processes. The average activity concentrations of 238U, 232Th, and 226Ra in all samples were higher than the worldwide averages, while 40K levels were lower. Isotopic ratio relationships showed accumulation of radionuclides in most samples except one sample lies in uranium leaching sector from the base layer of the wall. Uranium–Thorium (U–Th) dating revealed varying ages of uranium deposition: 42.43–119.90 ka in trench 1, 40.09–85.37 ka in trench 3, 63.92 ka in trench 2, and 106.50 and 325.80 ka in the top of wall, suggesting differential mobility of uranium. Hazard parameters like external radiation hazards (Hex < 1) were minimal and annual effective dose rates within acceptable limits, while, internal radiation hazards (Hin > 1) were a concern for samples from the top layers. All samples had absorbed dose rates higher than the global average, indicating elevated background radiation levels. [ABSTRACT FROM AUTHOR]

This study presents an investigation into the natural radioactivity levels of 238U, 232Th, and 40K using a thallium-doped sodium iodide (NaI(TI)) detector and associated radiological hazards in river sediments, specifically sand, which serves as a crucial building material in the KwaZulu-Natal Province of South Africa. The assessment aims to provide insights into potential radiological risks posed by the utilization of these sediments in construction activities. The mean activity concentrations of 238U, 232Th, and 40K are 145.33, 38.67, and 362.67 Bq kg–1, 124.64, 60.60, and 353.00 Bq kg–1, 144.00, 48.80, and 371.00 Bq kg–1, 92.95, 52.00, and 368.75 Bq kg–1, 133.55, 45.60, and 324.40 Bq kg–1, and 109.50, 52.50, 381.50 Bq kg–1 for Umngeni River, Umsunduzi River, Ashburton Sarupen, Hammersdale, Kwanjobekazi, and Cator Ridge, respectively. The obtained values of the radiological hazard indices (radium equivalent activity, external hazard index, internal hazard index, and activity utilization index) were below the world average values reported for building materials. Therefore, the studied samples are radiologically safe for use as building materials in the study area because they may not constitute any severe radiological hazards to residents. [ABSTRACT FROM AUTHOR]

A radiological baseline study was carried out by means of a computational analysis to evaluate the distribution of 226Ra, 232Th, 40K and 137Cs in samples of beach sand collected from the coastal areas of Antalya, Turkey. The results of the radiological risk assessment indicated that the calculated radiological risk for workers and tourists was below the level that could pose an endangerment to life or the safe operation. There was also no evidence of recent migration of 137Cs or other isotopes through precipitation, dust transport, or by indirect means such as sea currents. [ABSTRACT FROM AUTHOR]

The concentration of natural radionuclides 226Ra, 232Th and 40K in ceramic tiles manufactured in Poland is presented in this paper. The concentration of natural radioactive isotopes in the tested samples was determined using a low-level digital gamma ray spectrometer equipped with an HPGe semiconductor detector. The mean concentrations of 226Ra, 232Th and 40K in the analyzed samples were found to be 48 ± 3 Bq∙kg−1, 49 ± 3 Bq∙kg−1 and 476 ± 23 Bq∙kg−1, respectively. The world mean concentrations of these radionuclides (50 Bq·kg−1, 50 Bq·kg−1 and 500 Bq·kg−1, respectively) were not exceeded. Furthermore, in order to ascertain the level of gamma radiation exposure, fundamental radiation protection parameters were established: radioactivity concentration indicator/gamma ray indicator (Iγ), indoor dose rate (Din) and annual indoor effective dose (Ein). In the case of the investigated ceramic tiles, it was established that the parameters were not higher than the limit values, except the indoor gamma radiation dose rate which was found to be 1.5 times higher than the world average. Therefore, the findings of this study indicate that the utilization of the examined ceramic tiles in constructions should be approached with a degree of caution. [ABSTRACT FROM AUTHOR]

The current findings intended to assess the concentrations of natural radioactivity in water, sediment, and polychaete worms Marphysa madrasi and Namalycastis jaya in 12 distinct places along the southeast coast, of Chennai, Tamil Nadu, India. Mean gross alpha and beta activity in water samples from 12 locations ranged 0.43 ± 0.02 mBq/L and 1.65 ± 0.12 mBq/L, respectively. Similarly, for sediment samples, the average activity concentration for gross alpha and beta were 196.67 ± 0.23 and 1190. ± 0.34 Bq/Kg, respectively. The net radioactivity (gross alpha and gross beta) in Marphysa madrasi ranged 32.97 ± 0.13 & 528.24 ± 0.32 Bq/Kg, respectively and in Namalycastis jaya, the gross alpha activity's average ranged 29.07 ± 0.20 Bq/Kg and a gross beta activity average of 280.36 ± 0.23 Bq/Kg. According to the findings, the highest radiation levels were found in Nemilli (S7) for polychaetes. The least radiation levels in polychaetes were found in Pattinapakkam (S3) and Muttukaadu (S6) for Marphysa madrasi and Neelankarai (S4) for Namalycastis jaya. Conversely, across all 12 selected sites, the gross beta activity of water, sediment, and polychaete worms is greater than the gross alpha activity. [ABSTRACT FROM AUTHOR]

In this study, 47 coal samples from 16 selected coal mines from four provinces of Pakistan (Punjab, Sindh, Balochistan, and Khyber Pakhtunkhwa) were collected and analysed using a HPGe-based gamma spectrometry system. The objective of the study was to assess the occupational radiological risk from coal reserves in Pakistan. The 226Ra concentration values were found to be higher in coal samples collected from two locations in Meting-Jhumpir Coal Fields and one location of Chakwal Coal Field as compared to the recommended value by UNSCEAR (2000). The 232Th concentration values were found to be higher in coal samples collected from two locations in Padhrar Coal Field, one location in Dandot Coal Field and one location in Cherat Coal Field as compared to the recommended value by UNSCEAR (2000). The 40K values in all the analysed samples were found to be well below the recommended value by UNSCEAR (2000). From the radiological parameters, the values of the representative gamma index, which corresponds to an annual effective dose, were found to be higher than 1 Bq-kg−1 among the samples collected from Meting-Jhumpir coal fields, Chakwal coal field, Padhrar coal fields, Dandot coal fields, Hangu coal field, and Cherat coal fields. Excess lifetime cancer risk was estimated to be in the range of 0.07 × 10−3 − 0.34 × 10−3 with an average value of 0.18 × 10−3. The annual effective dose was estimated in the range of 0.01–0.07 µSv- y−1, which is below than the value established by the IAEA as the safe limit for the public in a planned exposure situation (1 mSv-y−1). It can be concluded that for some of the coal fields, the radionuclide concentration values and some of the radiological parameter values were found to be higher than the recommended values. Site-specific studies using direct radiation and radon measurement instruments are proposed for these coal fields to further investigate the radiological situation and its implications on workers and the public's health. Furthermore, we have used a theoretical approach to estimate the occupational health hazard based on the activity concentration of radionuclides in the coal samples, which needs to be validated with the direct-dose measurement techniques. [ABSTRACT FROM AUTHOR]

The formation of an aluminosilicate gel structure made of alkali-activated materials (AAMs) was conducted through an alkali-activation reaction of the solid precursors (fly ash, metakaolin, and wood ash). Fly and wood ash are by-products of the burning process of coal and wood, respectively. Alkali-activated materials of aluminosilicate origin, made from the different ashes, fly and wood, are very attractive research targets and can be applied in various technological fields due to their thermal stability, resistance to thermal shock, high porosity, high sustainability, and finally, low energy loss during production. In this paper, we evaluate physico-chemical properties, microstructure, and radiological environmental impacts when wastes that contain elevated levels of naturally occurring radionuclides (NORs) such as fly ash and wood ash are made into "green cements" such as AAMs. The determination of radionuclide content was performed by means of gamma-ray spectrometry. Results showed that the AAMs have a lower value in the activity concentration of radionuclides than raw materials. The external absorbed gamma dose rate was 74.7–107.3 nGy/h, and the external radiation hazard index values were in range of 0.445–0.628 Bq/kg. The results of the activity concentration measurements for alkali-activated materials indicate the potential of their safe application in building construction. In terms of the structural characterizations, the obtained alkali-activated materials were examined using XRD, DRIFT, FESEM, and TEM analyses. [ABSTRACT FROM AUTHOR]

This research assesses radioactivity in soil and coal samples around the Barapukuria coal-fired thermal power plant using a high-purity germanium detector. The range of activity of 226Ra, 232Th, and 40K in the studied soil samples were 14–75, 16–112, and 132–460 Bqkg−1, respectively and the respective activity in coal samples ranged from 14–30, 16–39 and 72–182 Bqkg−1. The majority of the hazard indices (absorbed dose rate, gamma index, effective dose and excess lifetime cancer risk) were higher than the world average, which shows that long-term exposure to terrestrial ionising radiation is not safe for coal miners and the local community. The presence of minerals like monazite and zircon, granitic type parent rock, bottom ash discharged adjacent on lowlands, fly ash deposition, different geochemical and physicochemical properties, dominant wind directions, the artificial contamination, meteorological conditions, leaching caused by rainwater- may have a crucial influence on NORM distributions. The quantitative results of this study have important implications for planning a larger and more modern coal-fired power plant, and this study's findings inspire municipal officials to restrict and monitor the release of fly ash nearby coal-fired power plants. In addition, it is essential to monitor the health of individuals (workers and locals) near the power plant. [ABSTRACT FROM AUTHOR]

The radioactivity concentrations in soil and medicinal plants from the Western Ghat region of India were determined using NaI(Tl) gamma spectrometry. The mean activity of 232Th, 226Ra and 40K in soil was found to be 15.0 ± 0.9 Bq kg−1, 35.8 ± 2.1 Bq kg−1 and 65.1 ± 2.2 Bq kg−1. In medicinal plants, the mean activity was found to be 9.3 ± 1.1 Bq kg−1, 28.4 ± 2.8 Bq kg−1 and 76.3 ± 3.7 Bq kg−1, respectively. The calculated transfer factors from soil to plant range from 0.70 to 2.88, 0.49 to 1.64 and 0.37 to 1.53 for 40K, 226Ra and 232Th, respectively. The mean transfer factor of 40K is greater than that of 226Ra and 232Th, showing a substantial increase of 40K in the plant by root uptake. The estimated average yearly effective dosage for the age group of 15 years and older in the study is much lower than the world average, whereas, for the age group of 5 years, the Mesua ferrea, Moringa oleifera, and Piper betle medicinal plant are above the recommended word average of 0.3 mSv y−1 for an individual as reported UNSCEAR, 2000. As a result, the consumption of medicinal plants does not pose a substantial health risk and is radiologically safe for intake by people aged 15 years and above, but not to individuals under the age of 5. The possible impact of natural radiation on a human has been assessed by calculating the hazard parameters and all values within the internationally recommended limits. The impact of soil physico-chemical properties on soil-medicinal plant transfer factor was assessed. The study will serve as a baseline data on the transfer of radionuclides from the soil to medicinal plants and from medicinal plants to human as well as guidelines on the development of herbal drugs for future pharmacological and phytochemical studies. [ABSTRACT FROM AUTHOR]

Radionuclide distribution and transfer factors in plants are decisive parameters used to evaluate radioactive contamination in the environment and its radiological health risks to humans. In this study, the activities concentration of 226Ra, 232Th, and 40K were measured using NaI(Tl) gamma-ray spectrometry on soils and on corresponding teff and wheat plant samples analyzed collected from Sakaro gold mining area from Reji kebele, Oromia, Ethiopia. The results of mean activity concentration of 226Ra, 232Th, and 40K samples analyzedzed in soil, teff, and wheat samples were found to be 33.05 ± 0.72, 13.7 ± 0.51 and 220.18 ± 0.61 Bq.kg-1, 3.93 ± 0.4,27 ± 0.61 and 148.3 ± 0.5 Bq.kg-1 and 3.22 ± 0.43, 4.59 ± 0.64 and 229.8 ± 0.5 Bq.kg-1 respectively. Results showed that the activity concentration of radionuclides in this study area was within the limit. The transfer factors from soil to cereal crops (teff and wheat) were compared with the study done in a different country of the world and its values were below unity except for 40K in wheat samples. The absorbed dose rate, annual effective dose rate, external and internal hazards index, lifetime cancer risk, and annual effective ingestion dose were estimated and were also compared with the internationally accepted values. It was found that none of the results exceeded the recommended limit value. [ABSTRACT FROM AUTHOR]

The activity concentrations of natural radionuclides 226Ra, 232Th and 40K in 19 soil samples from Zabili uranium exploration area were measured using a low-background digital gamma-ray spectrometer equipped with broad energy germanium detector. The activity concentrations of 238U, 232Th, and 40K range from 16.5 to 1110.9 Bq.kg−1, 19.45 to 76.97 Bq.kg−1, and 3.28 to 839.5 Bq.kg−1, with their mean values of 478.0, 58.9, and 562.5, respectively. In addition, radiological hazard parameters from the activity concentrations obtained were assessed by estimating radium equivalent activity, external and internal hazard index, indoor and outdoor absorbed gamma dose rate and the corresponding annual effective dose, effective dose rate to different body organs and tissues, and excess lifetime cancer risk. Derived radiological hazard indices have been revised in accordance with relevant national and international legislation and guidelines. The radiological hazard parameter values were found to be above the relevant limit values for soils. In order to investigate the distribution of radionuclides and associated health hazard parameters in the study area, a statistical study was performed. [ABSTRACT FROM AUTHOR]

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 α/β 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 µSv y−1. The average estimated cancer risk value depending on irradiations was calculated as 3.8 × 10−4 and 2.6 × 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 40K to the gross beta activity in drinking waters of the region was determined as 47%. [ABSTRACT FROM AUTHOR]

The current study is the first in-depth investigation into the natural radioactivity in soils and assessment of associated radiological risks to the population in Dakshina Kannada district of southern India. The specific activity of natural radionuclides was determined by NaI(Tl) gamma spectroscopy. The trace minerals found in the soil were detected by FTIR spectroscopy and their relative distribution is quantified by calculating the extinction coefficient. The specific activity of 226Ra, 232Th, and 40K range from 9.73 ± 0.7 to 59.97 ± 1.9 Bq kg−1 with a mean of 26.47 ± 1.2 Bq kg−1, 15.88 ± 0.8 to 78.8 5 ± 2.1 Bq kg−1 with a mean of 35.45 ± 1.2 Bq kg−1 and 147.06 ± 3.4 to 535.92 ± 6.7 Bq kg−1 with a mean of 403.11 ± 5.5 Bq kg−1, respectively. The normality of frequency distribution curves of radionuclide concentrations was confirmed by the Kolmogorov–Smirnov test. The estimated hazard indices were found to be within acceptable levels. Higher levels of 226Ra, 232Th and 40K in soils were detected in certain parts of Dakshina Kannada, which was linked to the mineralogy of the region. The specific activity of radionuclides was discovered to be dependent on the minerals kaolinite and calcite. The extinction coefficients of Kaolinite, Calcite, and Quartz in soil ranged from 33.11 to 63.98, 29.63 to 111.24, and 84.47 to 115.83, respectively. [ABSTRACT FROM AUTHOR]

Natural gypsum has been studied as a building material, and it has been discovered that it is one of the potential sources of indoor radioactivity due to naturally occurring radioactive elements in it. The levels of radioactive elements obtained in natural gypsum available in Abay gorge Dejen district were accomplished by a well shielded and calibrated gamma spectrometry with high purity Ge detector to evaluate the radiation hazard to workers in Dejen gypsum factories and dwellers in buildings decorated with gypsum products. The results of this study revealed that radioactive elements 238U, 232Th, and 40K are found in raw gypsum samples, with specific activity ranging from 1.47 ± 0.26 to 2.42 ± 0.37 Bqkg−1, 1.10 ± 0.26 to 2.60 ± 0.48 Bqkg−1, and 4.27 ± 1.92 to 44.53 ± 2.84 Bqkg−1, respectively. The mean specific activities are 1.90 ± 0.33 Bqkg−1 for 238U, 1.99 ± 0.39 Bqkg−1 for 232Th, and 28.16 ± 2.57 Bqkg−1 for 40K, which are significantly lower than the intercontinental approved values. All of the calculated radioactive risk indices were significantly lower than the global recommended values for building materials. The values of various radioactive indices indicate that the use of gypsum powder obtained from studied samples in the construction of residences is considered safe. [ABSTRACT FROM AUTHOR]

Natural radionuclide activity concentrations were measured in ceramic, gypsum, and brick samples from manufacturers, dealers, and construction sites in and around Addis Ababa, Ethiopia, using an HPGe detector. The study's main aim is to assess the activity concentration of building materials and their health impacts. Average activity concentrations (Bq kg−1) for 226Ra in ceramic, gypsum, and brick samples were obtained as 81 ± 1, 1.34 ± 0.17, and 39 ± 1, respectively. In ceramic, gypsum, and brick, concentrations of 232Th were obtained as 166 ± 4, 0.68 ± 0.18, and 103 ± 3, respectively, while concentrations of 40K were found to be 755 ± 16,15 ± 1, and 921 ± 24, respectively. Some of the materials that were tested, especially the ceramic samples, had slightly higher concentrations of radionuclides in comparison to other analysed samples. In all samples except ceramic, Raeq was < 370 Bq kg−1, which is the recommended limiting dose for bulk medium. Furthermore, the corresponding radiological parameters, such as absorbed dose, annual effective dose equivalent, excess lifetime cancer risk (ELCR), internal (Hin) and external (Hex) hazard indexes, gamma index (Iγ), and alpha index (Iα) were determined. The ELCR average values in this study are slightly higher than the global average, and the indoor and outdoor absorbed dose rates are greater than the limiting criteria of 84 and 59 n Gy h−1, respectively. Therefore, it is important to assess the potential radiation risk of ceramic samples, which should be used in a controlled manner to reduce gamma exposure to residents. Finally, the computed data could be used as a baseline to assess any future radiation exposure from construction materials. [ABSTRACT FROM AUTHOR]

The natural radioactivity level has been determined in a pilot site located at Solhan, in the Sahel region of Burkina Faso by means of gamma‐ray spectrometry in soil samples collected at a depth of 40 cm. The activity concentrations are estimated for 238U (range from 181.89 ± 3.62 to 191.37 ± 3.71 Bq·kg−1), 232Th (range from 44.92 ± 2.96 to 48.40 ± 3.25 Bq·kg−1), and 40K (range from 215.11 ± 6.13 to 238.60 ± 6.52 Bq·kg−1). The concentration of 238U present in these soil samples is five times higher than the world average, while the concentration of 232Th is almost the double of the world average. However, the concentration of 40K is particularly low in the study area, being almost half the world average. Additionally, calculations of the Th/K and Th/U ratios indicate the presence of a clay soil and insoluble uranium in the study area. These results made it possible to assess the radiological hazards on the human health. This allowed us to note that the average values of absorbed gamma dose rate in air (124.14 nGy·h−1), internal hazard index (1.24), annual effective dose equivalent (0.76 mSv·y−1), and excess lifetime cancer risk (5.34 × 10−4) are well above the maximum recommended limits. Only the mean values of radium equivalent activity (271.39 Bq·kg−1) and external hazard index (0.73) remain within the acceptable limit. [ABSTRACT FROM AUTHOR]

The 'As Low As Reasonably Achievable' (ALARA) principle is one of the 3 fundamental elements of radiation protection. Noting that ionising radiation is both encountered naturally in the environment as part of everyday life, and artificially as part of a range of practices, the ALARA principle aims to provide a means of optimising radiation exposures. Since the introduction of the principle the nuclear industry has had a good track record of progressively reducing occupational and environmental exposures across the nuclear fuel cycle. However, recent industry feedback has highlighted that as the exposures continue to decline, there is evidence that its application in the purest sense can result in a disproportionate outcome in terms of wider non-radiological hazards, and / or use of resources both physical and human. This is leading to a general push for day-to-day exposures in nuclear power generation to be far lower than other forms of energy generation, sectors such as medical or minerals refinement, or compared to exposures we get from natural sources of radioactivity. This is at great cost for what is a negligible improvement in public protection. With the ongoing concerns of climate change, many countries have made a commitment to embrace low carbon energy systems. In support of this ambition new nuclear power has been identified as a key part of the energy mix, highlighting the need to further develop the ALARA concept, to ensure a fair treatment of the perceived 'unique' radiological risk of nuclear power. This paper explores feedback from industry in relation to optimising radiation exposures in the Nuclear Industry. This includes the need for the evolution of the ALARA principle to ensure it embeds 'ALL Hazards', ensures a sustainable outcome, and is informed by stakeholder engagement, along with the need for a graded approach to radiological protection, to ensure that improvement plans are based on clearly defined-value benefits based on judgements of reasonableness, and not in response to external pressures to 'minimise exposure'. Feedback also highlighted the need to ensure we continue to tackle the Radiation Protection 'Skills Gap' and have sufficient skilled resources to meet the current and future needs of the industry in the context of climate change. [ABSTRACT FROM AUTHOR]

This research quantitatively evaluates the natural radioactivity levels and geological radiation hazard parameters of soil and rock specimens obtained from mining locations in North-Eastern Nigeria, by means of grammar-ray spectroscopy. There have been potential public health risks associated with the use of soil and rock from mining locations in North-Eastern Nigeria, specifically the study areas. A total of twenty-eight samples were systematically gathered from Nahuta and Kashere locations. Through gamma spectrometry employing a NaI (TI) detector, the natural radioactivity levels of 238U, 232Th and 40 K were determined for each and every sample. The findings indicated that the mean activity concentrations of 226Ra, 232Th, and 40 K in Nahuta are 46.13 ± 4.78 Bq/Kg, 34.10 ± 3.02 Bq/Kg and 473.94 ± 5.41 Bq/Kg for the soil samples respectively, and 32.91 ± 0.49 Bq/Kg, 40.70 ± 0.41 Bq/Kg, and 578.18 ± 4.28 Bq/Kg for the rock samples respectively. The corresponding mean activity concentrations of 226Ra, 232Th, and 40 K in kashere are 17.99 ± 4.18 Bq/Kg, 23.73 ± 1.78 Bq/Kg, and 191.65 ± 3.15 Bq/Kg, for the soil samples, and 20.24 ± 3.72 Bq/Kg, 29.09 ± 1.78 Bq/Kg, and 148.36 ± 3.15 Bq/Kg, for the rock samples respectively. An analysis of radiation risk parameters (D, AEDE, Raeq, Hex, Hin, AGDE and ELCR) has been conducted and findings explored. While the samples from the kashere region fall within the international recommended levels, elevated readings of certain radiation health parameters are observed in the Nahuta region, posing serious public health risk due to utilization of the soil and rock from this area in construction activities. [ABSTRACT FROM AUTHOR]

Methods for measuring alpha radiation during radon decay have found wide application in studies related to ecology, health protection, geological and geophysical surveys, as well as the possibility of predicting deformation processes in the earth's crust. Measuring radon levels in air and water is used to search for uranium deposits. Registration of low-intensity radiation and volumetric activity of radon seems to be a difficult task due to the insufficiently high sensitivity of detection systems. When creating instruments and devices for studying natural radioactivity, silicon detectors are widely used. The advantages of such detectors are simplicity, the ability to operate in a wide temperature range, under conditions of large flows of weakly ionizing alpha, gamma and beta radiation, and obtaining integral or averaged radon activity. Designed and manufactured highly sensitive detectors of large sizes installed in a radiometric device make it possible to measure and monitor low-intensity and low-energy radiation in various environments. The study of changes in radon concentrations in groundwater and soils can be used to predict earthquakes and destructive landslides caused by deformations of the earth's surface. Long-term monitoring of volumetric radon activity and gamma radiation activity was carried out on the territory of the Republic of Uzbekistan (Tashkent) and a connection between radon concentration and deformation processes in the earth's crust was identified. [ABSTRACT FROM AUTHOR]

To gain a deeper understanding of the conditions at decommissioned uranium mines, on-site monitoring of environmental radioactivity was conducted at a decommissioned uranium mine in southern China. The results showed that the average surface γ-ray dose rate in the mining area and surrounding regions ranged from 83.2 to 286.6 nGy h–1, and the average concentration of radon and its progeny in the air ranged from 23.1 to 66.5 Bq m–3 and 30.3 to 112.4 nJ m–3, respectively, which are below the national regulatory limits of China. After remediation, the uranium mine did not cause radioactive pollution to spread into the surrounding environment, indicating the effectiveness of remediation efforts over time. [ABSTRACT FROM AUTHOR]

Natural radioactivity was assessed in sediment samples collected along southern coastline of Tamil Nadu. Average activity concentrations of 238U, 232Th, and 40K were determined (29 ± 3, 218 ± 6, and 80 ± 5 Bq kg–1, respectively). Calculated parameters included radium equivalent activity (347 ± 12 Bq kg–1), absorbed dose rate (273 ± 10 nGy h–1), annual effective dose rate (0.33 ± 0.01 mSv y–1), external hazard index (0.94 ± 0.03), annual gonadal dose equivalent (1026 ± 35 mSv y–1), and excess lifetime cancer risk (1.17 ± 0.03). Multivariate statistical analyses were employed to examine correlations among the radioactive variables. The presence of heavy minerals in the samples was confirmed using X-ray diffraction. [ABSTRACT FROM AUTHOR]

This study investigates the natural radioactivity levels in Thiruvananthapuram, Kerala, focusing on uranium (238U), thorium (232Th), and potassium (40K) concentrations in rock samples collected from various locations. Rock samples were collected and analyzed using gamma ray spectroscopy with NaI(Tl) detectors to determine activity concentrations and radiological parameters. The results reveal varying concentrations of 238U (5.05 to 200.31 ± 11.85 Bq kg−1), 232Th (5.04 to 632.73 ± 37.44 Bq kg−1) and 40K (556.89 ± 3 2.95 to 2072.2 ± 122.61 Bq kg−1) with mean values of 49.12 Bq kg−1, 257.71 Bq kg−1, and 1451.56 Bq kg−1 respectively. Radiological parameters (Raeq, DR, AED, H(in,out), GI, RLI, ELCR(in, out), AUI, AGEDE) were also calculated. Correlation and ratio analyses further highlight relationships between uranium, thorium, and potassium concentrations, revealing their geological associations and implications for radiological hazards. This study underscores the importance of monitoring natural radioactivity in urban environments to mitigate potential health impacts and ensure public safety. [ABSTRACT FROM AUTHOR]

This study investigates the levels of natural and artificial radioactivity in rice samples collected from various local markets in Islamabad, Pakistan. The 226Ra, 232Th, and 40K activity concentrations were measured through gamma-ray spectrometry with a NaI(Tl) detector. The average activity concentrations were 1.67 ± 1.19 Bq kg−1 for 226Ra, 3.31 ± 1.83 Bq kg−1 for 232Th, and 88.51 ± 11.65 Bq kg−1 for 40K. Calculated radium equivalent (Raeq) values ranged from 7.35 to 18.08 Bq kg−1, with a mean value of 11.11 Bq kg−1, all below the permissible maximum of 370 Bq kg−1. The absorbed dose rates ranged from 6.85 to 16.39 nGy h−1, with an average of 10.64 nGy h−1, falling below the acceptable limit of 51 nGy h−1. The outdoor and indoor radiation hazard indices (Hex and Hin) had mean values of 0.03, both below the threshold value of one. The external and internal hazard indices (Iγ and Iα) were both 0.088, also below the critical value of one. The excess lifetime cancer risk (ELCR) ranged from 0.28 to 0.11, with a mean value of 0.18, which is less than the critical value of one. Overall, the radioactivity levels in the analyzed rice samples are within the acceptable limits set by the International Commission on Radiological Protection and are below global averages. These results offer important insights into the radiological safety of rice consumption in the study area. [ABSTRACT FROM AUTHOR]

Soil samples were collected from vegetable agricultural areas in and around Addis Ababa, and their levels of radioactivity were measured. Gamma spectrometry with high-purity germanium detector was used to quantify radioactivity level. The average concentration of 226Ra, 232Th, and 40K were 32.8 ± 2.1, 62.4 ± 4.4, and 544.3 ± 23.3 Bq kg−1 respectively. The mean values of 232Th and 40K are higher, whereas the value of 226Ra is comparable with world average values. Radiological hazard indices, including radium equivalent activity (Ra eq), absorbed dose rate (D r), outdoor annual effective dose equivalent (D eff), external hazard index (H ex), internal hazard index (H in), and gamma radiation representative level index (I γ), were calculated based on the activity concentration of 226Ra, 232Th and 40K. The mean values were 163.9 Bq kg−1, 78.7 nGy h−1, 0.10 mSv y−1, 0.44, 0.53, and 0.60 respectively. All indices are lower than global recommended limit values. These results revealed that radiation hazard due to radionuclides in the soil of the study area is insignificant. [ABSTRACT FROM AUTHOR]

The enhancement of natural radioactivity in groundwater, specifically in natural mineral water, is related to the lithological formations through which water bodies or courses pass. Although natural mineral waters are exempt from monitoring for radioactive substances according to Council Directive 2013/51/EURATOM, this study focuses on the radiological characterization of natural mineral water under Spanish Royal Decree 3/2023. The water studied was taken from Catalan aquifers with different lithological characteristics (sedimentary, metamorphic or granitic) and is sold on local markets. Moreover, radiological data on the water was correlated with its lithological origin and the health risk for different age groups was assessed. Our results showed that of the 26 natural mineral waters studied, 10 exceeded gross alpha screening value (100 mBq/L), all from granitic aquifers. Further research on natural individual radionuclides was conducted on these ten samples. 234U and 238U were at around 1100–1600 mBq/L. In addition, 210Pb was found in two samples, which also presented the highest 226Ra activity, associated with granitic bedrock and the presence of 210Po. The annual effective dose was 179.0 µSv/year and 145.9 µSv/year, exceeding 100 µSv/year mainly due to the contribution of 210Pb > 234,238U > 210Po > 226Ra, in this order. After assessing the lifetime cancer risk, these two samples were determined not to pose a health risk due to ingestion. Although no radiological monitoring is required for natural mineral water, further surveillance is recommendable. [ABSTRACT FROM AUTHOR]

Levels of natural radioactivity due to 40 K, 232Th, and 226Ra in limestone deposits and corresponding surface soil samples from the Nkalagu community of Ebonyi State were investigated. Gamma spectroscopic analysis using a NaI (TI) detector was employed to measure the activity concentrations (ACs) of the natural radionuclides in the collected samples. The average AC of 226Ra, 232Th, and 40 K was found to be 64.62 ± 11.63, 54.27 ± 8.52, and 313.06 ± 25.33 Bq/kg, respectively, in limestone, whereas in the soil, the value was 60.80 ± 11.71, 44.97 ± 10.74, and 185.90 ± 18.20 Bq/kg, respectively. Except for 40 K, the obtained mean ACs of the radionuclides were in excess of the worldwide averages reported by the United Nations Scientific Committee on the Effect of Atomic Radiation (UNSCEAR). The mean value of Raeq, Hex, Hin, Iγ, and AUI was obtained as 166.33 Bq/kg, 0.45, 0.62, 1.18, and 1.28, respectively, in the limestone, and 139.42 Bq/kg, 0.38, 0.54, 0.98, and 1.12, respectively, in the surface soil. The radiation doses in limestone ranged from 120.78–168.89 nGyh−1 and 63.86–88.88 nGyh−1 for indoor and outdoor, respectively, whereas in the soil, the range was 104.47–129.77 nGyh−1 and 54.60–68.02 nGyh−1 for indoor and outdoor, respectively. The total annual effective dose ranged from 0.671 to 0.937 mSvy–1 with an average of 0.800 mSvy–1 in limestone and 0.579 to 0.720 mSvy–1 with an average of 0.667 mSvy–1 in the soil. Values of representative gamma index and activity utilization index, and indoor and outdoor radiation doses in limestone were above the recommended world average of ≤ 1, and 84 nGyh–1 and 59 nGyh–1, respectively, suggesting a restriction in the use of the limestone in construction of houses. The study therefore recommends that the use of limestone in building construction, especially in house interiors, should be discontinued. [ABSTRACT FROM AUTHOR]

To establish a radiological national reference for agricultural soil across Tunisian oases and assess the risk to human health associated with date consumption, with a focus on comparing the impact of traditional and modern fertilization, radiological parameters and activity levels of 22⁶Ra, 232Th, and 4⁰K were determined for 27 oases. These oases were located in three southern Tunisian governorates. The activity concentration of 22⁶Ra, 232Th, and 4⁰K was measured using a 3 × 3 inch NaI(Tl) scintillation detector, which was found to be 21.82 ± 1.0 Bq kg - 1 , 26.51 ± 1.1 Bq kg - 1 , and 559.21 ± 23.0 Bq kg - 1 , respectively, for traditional oases and 26.56 ± 1.2 Bq kg - 1 , 24.45 ± 1.1 Bq kg - 1 , and 661.28 ± 26.3 Bq kg - 1 , respectively, for modern oases. In addition, ambient dose equivalent rate was measured during sampling using a multipurpose hand-held radiation CsI(Tl) detector, which was found to be 0.075 µSv/h in traditional oases and 0.078 µSv/h in modern oases. The resulting radiological parameters and activity concentrations were then compared to results from neighboring countries and the average soil activity worldwide. [ABSTRACT FROM AUTHOR]

In this paper, an investigation focused on assessing the radon exhalation, the natural radioactivity level, and the mineralogy of natural stones of particular historical–artistic interest employed as building materials was carried out. The Closed Chamber Method (CCM) with the Durridge Rad7 apparatus for short-lived radon progeny alpha spectrometry and High Purity Germanium (HPGe) gamma spectrometry were used to determine the radon exhalation rate and specific activities of 226Ra, 232Th, and 40K, respectively. Furthermore, several indices were evaluated to determine the radiological risk due to radiation exposure from the investigated natural stones, i.e., the absorbed gamma dose rate (D), the activity concentration index (ACI), and the alpha index (Iα). Finally, X-ray diffraction (XRD) and Micro-Raman Scattering (MRS) investigations were performed to correlate the chemical composition and mineralogical characteristics of natural stones with the radon exhalation rate and the natural radioactivity content. It is worth noting that the findings from this study can be used to guide future research into the background levels of radioactivity in stones used as construction materials. [ABSTRACT FROM AUTHOR]

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Galala limestone is widely used for construction and ornamental purposes and is known throughout the world under many commercial names, including Galala White, Galala Golden, Galala Creama and Galala Classic. Using a HPGe spectrometer, about 20 samples from the marble building industry were radiometrically analyzed and the gamma radiation emitted by the radionuclides 238U, 232Th and 40K was evaluated. The measurements performed showed that the concentrations of these radionuclides were 15 ± 13, 6 ± 4 and 1100 ± 330 Bq kg−1, respectively. It's important to note that all these recorded values do not exceed the internationally reported average levels of 33, 45 and 412 Bq kg−1for each individual element. The annual effective dose (AED) was estimated. The mean value of AED, 0.07 mSv/y, is comparable to the permissible average of 0.07 mSv/y, respectively. The relationship between radionuclides and their radiological hazard characteristics was studied using various multivariate statistical techniques such as Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). The results indicate that the main contributors to the radiological hazard associated with marble are uranium and potassium. As a result, the use of marble in building materials may not pose a significant risk to public health.

The study aims to assess the marine environmental hazards resulting from some industrial activities areas being found at the Suez Bay. The survey was done to select five industrial locations along the studied areas where different water and sediment samples were collected during September 2020. The study methods showed that different concentrations were measured in the collected water and sediment samples, such as; Al, Fe, Mn, Hg, Cd, Cr, Co, Mo, V, Pb, Ni, Cu, Zn, where the digested samples were measured by using Inductively Coupled Argon Plasma spectroscopy (ICAP 6500 Duo), while the natural radioactivity concentrations of the selected radio-nuclides such as 238U, 226Ra, 232Th, 40K, were measured in both water and sediments samples by using Hyper germanium detector, as the radiological risk assessment of different samples was detected by using ERICA modeling software. The study results showed that the concentrations of the measured trace elements in the selected five industrial sites were slightly higher than the standard limits, while the measured radioactivity concentrations of the selected radio-nuclides in both water and sediment samples were below the standard limits. The results showed that the calculated distribution coefficient of the selected trace elements was (Kd Metal Pollution Index < 3), which indicated that the measured trace elements were more dissolved in the aqueous than the sediment medium. The study used the mean probable effect Level (m-PEL-Q) for estimating the metal concentration hazards in the sediment samples at the selected sites, where these values were ranged from 0.04 to 0.1, indicating that the combined concentration effects for these metals were caused 9% toxic probability. The study showed that both the calculated quotient risk (QR) and dose rate values of the marine organisms which were being calculated by the ERICA model were below the recommended limits. [ABSTRACT FROM AUTHOR]

Abstract The aim of the current study is to evaluate the radioactivity estimate the radiological risk of some granites and marbles rocks and explaining the cause of increased radioactivity in some types of rocks. The radioactivity of some granites and marbles produced in Egypt were determined by using a Germanium detector. Three types of marble (Breshia, Galala, and Trista) and three types of granite (Gandola, White Halayeb, and Red Aswani) were collected. All marble samples show low radioactivity with average activity concentrations of 20 ± 2, 4.50 ± 0.5, and 6.70 ± 1.2 Bqkg− 1 for 226Ra, 232Th, and 40K respectively. Granite samples have higher activity concentration with averages of 152 ± 7, 129 ± 8, and 1228 ± 15 Bqkg− 1 for 226Ra, 232Th, and 40K respectively which exceed the world average values of soil (32,45,412 Bqkg− 1 for 226Ra, 232Th, and 40K respectively) excluding Granite G.2 (white Halayeb) as it shows an insignificant level of radioactivity. The annual effective doses of marble samples Breshia, Galala, and Trista were measured to be 4.42 ± 0.4; 158 ± 14 and 153 ± 15 µSvy− 1, and 1008 ± 147, 80 ± 7 and 987 ± 45.0 µSvy− 1 for the granite samples Gandola, White Halayeb and Red Aswani respectively. The radiation hazard parameters show a higher value for granite samples than marble samples, primarily due to the presence of potassium feldspar minerals in these types of granites. marbles were observed to be radiologically safer than granite because they possess a neglected 40K content and a trace quantity of uranium and thorium. Moreover, the minimum potassium content is enough to make a rock radiological unsafe due to 40K only being determined to be about 13.2%.

Natural background radiation exposure is an inevitable occurrence on Earth, and humans are exposed to radiation in their surroundings whether consciously or unconsciously. However, increased artisanal and illegal mining could harm the local environment and increase background radiation levels, affecting the community's overall health. This study assessed the activity concentration of primordial radionuclides (226Ra, 232Th, and 40K) from soil samples obtained from Mamara Jidda and Waja tin mine sites in Nasarawa State, Nigeria, and its risk to human health. The gamma spectroscopy using a Sodium iodide-thallium activated detector was used to measure the activity concentrations of primordial radionuclides in the surface soils/sediments samples. The activity concentrations of 226Ra, 232Th, and 40K for Mamara Jidda and Waja were found to be within the range of 4 - 18 Bq kg-1, 41 - 105 Bq kg-1, and 524 - 717 Bq kg-1; 13 - 40 Bq kg-1, 75 - 134 Bq kg-1, and 591 - 882 Bq kg-1 respectively. The average values show that 40K and 232Th concentrations are above the recommended limit set by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) in Mamara Jidda and Waja mine sites. The annual gonadal dose equivalent (AGDE), annual effective dose rate (AEDE), radium equivalent (Raeq), absorbed dose rate (D), and external hazard index (Hex) for Mamara Jidda and Waja were found to be 0.56 mSv yr-1, 0.10 mSv yr- 1, 588.58 Bq kg-1, 78.26 nGy hr-1 and 0.46; 0.73 mSv yr-1, 0.13 mS yr-1, 742.74 Bq kg-1, 103.72 nGy hr-1 and 0.61 respectively. The AEDE and Hex are below the recommended safety limits. However, the high values of AGDE in both mining sites and D in Waja mine demonstrate that with continuous exposure to radiation, a significant genetic impact is eminent to the miners and inhabitants of these areas. Also, the Raeq values for both mines suggest that their soils are unsafe for use as building materials.

In the city centre of Isparta, located in the southwestern part of Türkiye, indoor radon concentrations and gamma dose rate levels were observed above the world and country averages. For this reason, the determination of the natural radioactivity levels in soil samples of Isparta province is of great interest. In the present study, the activity concentrations of radionuclides (namely 226Ra,232Th, 40K and 137Cs) were investigated in the soil samples collected from 72 different points including the city centre and 12 towns of Isparta by using a gamma spectrometer with a high-purity germanium (HPGe) detector. The activity concentrations of 226Ra,232Th, 40K and 137Cs radionuclides in the samples were found in the range of 4.08 ± 0.39–69.84 ± 1.43 Bqkg−1, 2.63 ± 0.28–65.66 ± 1.41 Bqkg−1, 44.48 ± 3.17–452.38 ± 9.65 Bqkg−1 and 0.28 ± 0.18–19.10 ± 0.61 Bqkg−1 respectively. The averages of all the measurements were determined as 15.69 ± 0.72 Bqkg−1 for 226Ra, 15.40 ± 0.78 Bqkg−1 for 232Th, 210.60 ± 6.22 Bqkg−1 for 40K and 3.44 ± 0.31 Bqkg−1 for 137Cs. Although these values were below the country and world averages, it was revealed that the 226Ra and 232Th activity concentrations in the city centre exceeded the national and world averages. In addition, radiological risk maps of the analysed radionuclides were produced for the first time, covering all towns within the Isparta province. To evaluate the radiological hazards resulting from natural radionuclides, external hazard index (Hex), absorbed dose rate (D), annual effective dose equivalent (AEDE), male and female lifetime cancer risk (LCR) values were also calculated. The outcomes of this study revealed that all the radiological parameter averages for Isparta were lower than the world and country averages but the calculation results for the city centre displayed the opposite of this situation except for the external hazard index.

The present study concerned with the activity concentrations of natural radionuclides (238U, 234U, 230Th, 226Ra, 232Th, 40K and, 235U) in ten sedimentary rock samples collected from fault zone, Gabal Um Hamd, southwestern Sinai, Egypt. These samples were investigated to study their behavior during a part of geologic time. The activity concentrations were measured using γ-ray spectrometry (HPGe detector). The investigated samples were analyzed for major oxides using the XRF technique. The results demonstrated high average activity concentrations of 238U, 234U, 230Th, 226Ra, 232Th, 40K and, 235U than the worldwide average values as reported by UNSCEAR 2008. Theil diagram showed that there are accumulation and leaching of uranium in some samples in the two sides of the fault zone. It is noticed that the ages of uranium depositions for the samples collected from the downthrown of the fault zone vary from 121.5 to 440.1 ky, while for the sample collected from the upthrown of the fault is 210.9 ky. The 230Th/232Th activity ratios range between 4.55 and 91.04 for downthrown samples and between 4.75 and 6.05 for upthrown samples which are smaller than 20 except for two samples, indicating a contamination of the samples by detrital 230Th. After subtraction of the detrital 230Th, the corrected ages for downthrown samples vary from 119.1 to 231.7 ky while for upthrown samples vary from 164.4 to 390 ky.

There is a lack of available data on the radioactivity levels of these materials, despite the potential risks they may pose to patients, dental technicians, and dentists. A total of forty samples were collected from different dental markets in Egypt. Using an NaI(Tl) detector, the gamma-ray spectrometer measured the activity levels of uranium-238, radium-226, thorium-232, and potassium-40. The findings revealed that the mean concentration of 238U (below the minimum detectable activity, MDA), 226Ra (135 ± 5 and 132 ± 5 Bq/kg), 232Th (187 ± 4 and 243 ± 8 Bq/kg), and 40K (1560 ± 52 and 2501 ± 89 Bq/kg) in feldspar and zirconia (ZrO2) dental ceramic samples, respectively, were all within the limits established by the International Organization for Standardization (ISO) and the European Commission (EC). The use of feldspar and zirconia dental ceramics to restore all teeth would result in an estimated maximum beta dose of 1.5 mGy/year to the oral tissue. The results suggest that there is no cause for concern regarding any additional beta dose to the oral cavity from the use of feldspar and zirconia dental ceramics.

AbstractGamma spectrometry was employed to determine activity concentration of naturally occurring radionuclides 238U, 232Th and 40K in sediment samples collected from Vellanathuruthu to Thumpoly of Kerala Coast using NaI(Tl) detector and to evaluate the radiation hazards. The levels and distribution of radionuclides in sediments from this coastal area have been determined. The activities ranges and mean (in bracket) values for 238U, 232Th, and 40K are 78.92 to 1493 Bq kg−1 (552.63), 94.76 to 2856.46 (851.24) Bq kg−1 and 30 to 2399.20 (678.61) Bq kg−1 respectively. The mean activity of 238U, 232Th, and 40K are higher than the global average values (35 Bq kg−1 for 238U, 400 Bq kg−1 for 40K, and 30 Bq kg−1 for 232Th) of these radionuclides in the sediment and it may be due the presence of rich deposits of black sands. The radium equivalent activity was estimated to range from 216.74 to 5762.48 Bq kg−1 (1822.17). The average absorbed dose rate was determined to vary from 94.96 to 2515.83 nGyh−1 (797.97) and the annual effective dose was estimated to range from 0.12 to 3.09 mSvy−1 (0.98). Additionally, it was estimated that the average external hazard index was 4.92 and the average internal hazard index was 6.41 respectively. The computed radiation indices for all samples were compared to internationally accepted standards, showing that they are above the recommended limits. The results of the present investigation indicate that the radioactivity in the region is slightly above the global average values. [ABSTRACT FROM AUTHOR]

Beach sediments are mineral deposits formed through weathering and erosion of either igneous or metamorphic rocks. Among the rock constituent minerals are some natural radionuclides that contribute to ionizing radiation exposure on Earth. Kolatoli and Kuakata are the two major beaches with heavy mineral deposits and important tourist sites in Bangladesh. Natural radioactivity in Kolatoli and Kuakata beach sand deposits along the southern coast of Bangladesh was assessed and compared to identify the sources, causes, and possible environmental impact. Result shows most of the radionuclides have higher activity concentrations than the background level, and the activity varies with the sample locations. The dominant radionuclides were found to be the radionuclides of thorium series i.e. Th-232 and Ra-228 followed by uranium series and K-40. The radioactivity in Kolatoli beach sands was observed to be much higher than Kuakata beach due to the presence of a higher content of heavy minerals i.e. illmenite, rutile, zircon, garnet and monazite. Furthermore, monazite and zircon are the two radioactive minerals that are considered to be the main contributors to the radioactivity in Kolatoli beach sand. These minerals are dominated by the activity of thorium series radionuclides i.e. Th-232 and Ra-228 surpass the activity of all other radionuclides such as U-238, U-234, Th-230, Ra-226, Po-210, and K-40. However, major contribution of radioactivity in Kuakata beach sand comes from uranium series radionuclides such as U-238, U-234, Ra-226, and Po-210. Beach morphology, sedimentological, and geochemical evolution of those minerals might be important areas of further study for the radioactivity monitoring activity in those areas. [ABSTRACT FROM AUTHOR]

Spergularia rubra (L.) J. Presl & C. Presl has a mycorrhizal resistance that leads to increased uranium uptake. The results show that 35% of the 238U is retained in the carbonate fraction and 59% in the residual or non-reactive fraction. 226Ra shows a different pattern with an average association of 19% in the organic matter fraction, 10% in the carbonate compounds and the remaining 71% in the residual fraction. The relationships between the activity concentrations of 238U and 226Ra in the soil fractions and in Spergularia were found to be statistically representative of the carbonate and organic matter fractions, respectively. [ABSTRACT FROM AUTHOR]