Activity Concentrations Of 226Ra Research Articles

Natural Radionuclides Concentrations and Associated Radiation Hazard of Some Building Rocks Used in Taiz City, Yemen

Building materials comprise a diverse range of natural rocks that contain varying mineral components including radionuclides. Gamma spectrometry-based high-purity Germanium detectors were utilized to measure the activity concentrations of natural radionuclides: Radium-226 (226Ra), Thorium-232 (232Th), and Potassium-40 (40K) in various building rock samples found within and surrounding Taiz city. The activity concentrations of 226Ra, 232Th, and 40K vary from 27.79 ± 0.77 to 234.49 ± 3.13 Bq.kg-1, 25.82 ± 0.40 to 415.31 ± 2.47 Bq.kg-1, and 457.91±2.61 to 1139.56 ± 5.43 Bq.kg-1 with overall average value of 71.55 Bq.kg-1, 93.87 Bq.kg-1, 966.88 Bq.kg-1 respectively, these values were higher than the permissible thresholds. Furthermore, several radiation hazard indices were estimated including the radium equivalent (Raeq), the external hazard index (Hex), the internal hazard index (Hin), the gamma level index (Iɤ), the dose rate(Dɤ), the annual effective dose equivalent (AEDE), the excess lifetime cancer risk (ELCR), and the annual gonadal dose equivalent (AGDE). The findings illustrated that Basalt rocks have the minimum values of radiation hazard indices while the Himatite rocks have the maximum values of radiation hazard. The average values of radiation risks for most of building rocks fall below the recommended limits for safety. Based on the Radiation hazard indices of building rock samples, it can be concluded that with the exception of hematite rocks, all the examined rocks are considered safe for use in construction materials and pose non-significant radiation risks. The awareness about natural radioactivity levels of building rocks is critical for planning and performing strategies in radiation safety of buildings.

Evaluation of radioactivity and radiological parameters in soil samples in Isparta, Türkiye

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.

Evaluation of radioactivity concentration in farm fresh milk and concomitant dose to consumer

In this study, activity concentrations of natural radionuclides in 28 raw milk samples collected from different dairy farms in Dhaka city of Bangladesh were measured using a high-purity germanium (HPGe) detector for the first time. The activity concentration of 226Ra, 232Th, and 40K in the investigated fresh milk samples ranged from BDL (Below detection level) to 26 ± 1.6 Bq/kg, BDL to 11.7 ± 3.3 Bq/kg and 101 ± 17 to 384 ± 32 Bq/kg, respectively. No artificial radionuclides were found in the investigated samples. Present results show inline within the range of available data in the literature. Annual committed effective doses were estimated following the consumption characteristics of raw milk by city population, values are found within the limiting range recommended by international organizations due to consumption of foodstuffs. Additionally, real-time gamma-ray dose rate in the farms/sampling locations was found in the range of 0.12 ± 0.01–0.20 ± 0.01 μSv/h by using a digital gamma survey meter (Gamma Scout) and the calculated maximum annual effective dose due to outdoor absorbed dose was found to be 0.25 mSv/y, which shows lower than the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) recommended limit of 2.4 mSv/y. This study indicates that the concentration of radionuclides in the farm fresh milk of Dhaka city does not pose any unwanted risk to public health, and it is safe to consume by both children and adults with the current intake level.

Radiometric and health risk assessment of building materials collected from Tamil Nadu using gamma-ray spectrometry

ABSTRACT The radiometric analysis was carried out on different building materials collected from Tamil Nadu, using gamma-ray spectroscopy with NaI(Tl) detector. The mean activity concentrations of 226Ra (38 Bq kg−1) and 40K (643 Bq kg−1) in all building materials were higher than the world-populated weighted average of 33 Bq kg−1 and 420 Bq kg−1, respectively, while for 232Th (28 Bq kg−1), it was lower than 45 Bq kg−1, as reported by UNSCEAR (2000). These results were compared with similar studies carried out around the world. The calculated radiological parameters, radium equivalent activity (127 ± 11 Bq kg−1), absorbed dose rate (61 ± 5 nGy h−1), annual effective dose equivalent (0.30 ± 0.02 mSv y−1), internal and external hazard index (0.45 ± 0.04 and 0.34 ± 0.03) and activity utilisation index (0.74 ± 0.08), are within the world-populated weighted average and safest limits. Moreover, the radiogenic heat production rate (RHP) due to the natural radionuclides in the building materials was calculated, and the total RHP was 0.94 µWm−3. Multivariate statistical analyses, such as Pearson correlation analysis, hierarchical cluster analysis and factor analysis, were implemented on activity concentration and radiological parameters to evaluate the interrelationship between them.

Activity concentration of NORM at reclaimed ex-coal mines in South Sumatra, Indonesia

Unbeknownst to us, natural radiation is in close proximity to human existence. Post-mining practices can generate naturally occurring radionuclides that have the potential to cause radiological effects on human health. This study utilized soil samples obtained from ex-mining reclamation land in Banko Barat, South Sumatra Province, to assess the concentration of natural radioactivity and the corresponding radiation dose. Eight composite soil samples were collected from reclaimed land. The samples underwent processing and analysis through gamma spectrometry in order to ascertain the activity concentration of the radionuclides 226Ra, 232Th, and 40K. The RESRAD-ONSITE 7.2 software utilizes the activity concentration of soil samples as an input parameter to accurately predict the dose rate for workers. The projected dose rate was determined by considering four routes of exposure: external gamma radiation, inhalation, radon, and ingestion of soil. The measured activity values of soil samples from reclamation land for 226Ra ranged from 25.6704 ± 0.5082 to 58.8555 ± 0.6917 Bq/kg. The activity values for 232Th ranged from 30.5546 ± 0.1757 to 42.53020.3004 Bq/kg. Lastly, the activity values for 40K ranged from 533.902 ± 6.4023 to 988.081 ± 9.6948 Bq/kg. The total effective dose rate measured in the reclaimed land falls between 0.08673 and 0.1469 millisieverts per year. The value does not surpass the maximum limit set by BAPETEN, which is one mSv/year. Therefore, no additional protective measures are required for workers.

Radiological Assessment and Potential Health Risks of Tailings from Komu, Southwestern Nigeria

There are reports that radionuclides found in mining tailings pose significant challenges to the natural environment and cause health risks to humans. The study investigated the levels of activity concentrations of 226Ra, 232Th and 40K radionuclides, as well as radiological hazard indices in tailings sourced from Komu, a community emblematic of mining activities in the Southwest of Nigeria. Thirty (30) tailing samples were collected and analysed by a High-purity Germanium (HpGe) detector. The results revealed high activity concentrations of these radionuclides exceeding global averages and indicating potential health risks. The activity concentration of 226Ra ranged between 312.07 and 851.14 Bq/kg, with an average of 652.86 Bq/kg. Similarly, the activity concentration of 232Th ranged between 33.31 and 160.10 Bq/kg, with an average of 116.26 Bq/kg. In addition, the activity concentration of 40K ranged between 96.11 and 1184.65 Bq/kg, with an average of 717.53 Bq/kg. The radiological hazard indices considered in this study exceeded the internationally accepted safety limit for building construction materials. These findings indicate heightened exposure risks, emphasizing the need for regulatory measures to mitigate hazards associated with tailings sourced from Komu, particularly for building construction purposes.

Assessing the radiological hazards due to radionuclides in sediments and tailings around Kilembe copper mines, Western Uganda

ABSTRACT Copper mining in Kilembe Valley, Western Uganda, between 1956 and 1982 resulted in multiple tailing sites, raising concerns about potential increases in the natural background radiation. In this study, the radioactivity concentrations of 226Ra, 232Th, and 40K in 31 sediments and tailing samples from the Kilembe copper mines area were determined using HPGe-based gamma spectrometry. The mean activity concentrations of 226Ra, 232Th, and 40K in sediment samples were 38.6 ± 8.9, 37.4 ± 7.8, and 708.0 ± 147.3 Bq kg−1, respectively. While in tailing samples, the mean values were 171.3 ± 31.7, 34.8 ± 14.9, and 792.4 ± 208.2 Bq kg−1, respectively. These values exceeded global averages of 35, 30, and 400 Bq kg−1 for 226Ra, 232Th, and 40K, respectively. To assess the radiological hazards due to radionuclides in sediments and tailings, several parameters such as the radium equivalent activity (Raeq), external hazard index (Hex), internal hazard index (Hin), gamma representative index (Iγ), absorbed dose rate (D), total annual effective dose (Etot), and total excess lifetime cancer risk (ELCRtot) were determined. In sediments, most of these hazard parameters were above the world’s average values, except Raeq, Iγ, Hex, and Hin. While in tailings, all the hazard parameters surpassed the global average values except Raeq and Hex. Pearson correlation coefficient and hierarchical cluster analysis showed that 226Ra was the main contributor to the assessed radiological hazards. The study suggests potential radiological risks linked to natural radioactivity from sediments and mine tailings, especially when used as building materials.

Natural radionuclides and radiological risk assessment in the stream and river sediments of a high background natural radiation area Kanyakumari, India.

The Kanyakumari coast is known to be a high background natural radiation area due to the placer deposits of heavy minerals such as ilmenite, monazite, and rutile. The Kanyakumari river sediments that could be the source of the elevated amounts of natural radionuclides in the coastal sands have been studied in this paper. The activity concentrations of primordial radionuclides 226Ra, 232Th, and 40K were determined using high-purity germanium (HPGe) gamma-ray spectrometry. The mean activity concentrations of 226Ra, 232Th, and 40K were found to be 75Bqkg-1, 565Bqkg-1, and 360Bqkg-1, respectively. The mean absorbed dose rate was 395 nGy h-1. Radiological hazard parameters were studied and compared with the world average values. The contribution of 232Th to the total dose rate was found to be higher than that of the two other radionuclides. The high mean ratio of 232Th/226Ra suggested an enrichment of 232Th and the occurrence of 226Ra leaching due to an oxidizing environment. Principal component analysis (PCA) was carried out for the radionuclides in order to discriminate the source of the sediments. This study provides new insights into the distribution of natural radionuclides in sediments of rivers and streams.

Gamma Ray Spectroscopy Analysis of Sediments of Coastal Areas in Ennore, Tamil Nadu

Objectives: This research focuses on the determination of the natural radionuclides radium, thorium, and potassium in the twenty-six sediment samples collected at the sea, beach, and creek regions of Ennore Port. Methods: The activity concentrations of 226Ra, 232Th, and 40K were determined using gamma ray spectrometry with a high-purity germanium (HPGe) detector. Findings: The average activity concentrations of 226Ra, 232Th, and 40K were in the descending order of 40K (397.58 Bq kg-1) > 232Th (65.83 Bq kg-1) > 226Ra (18.28 Bq kg-1). The estimated average values of radiological parameters such as radium equivalent activity (143.04 Bq kg-1), absorbed dose rate (64.91 nGy h-1), annual effective dose equivalent (0.32 mSv y-1), and external hazard index (0.39) were lower than the respective world average values, reported by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR, 2000). Moreover, the representative level index and annual gonadal dose equivalent were slightly higher than the world average value. Hence, this research proved that the study area is radiologically safe for humans and the environment. Novelty: A location and sample collection-based novelty is approached to carried out the work. Sea sediments were also collected along with samples from creek and beach regions in order to examine the dispersion of natural radionuclides from land to marine environments. The samples from the beach and creek regions were collected using a Peterson grab sampler. Especially in the sea region, the samples were collected using a Van Veen grab sampler at a depth of 4 m and a distance of 10 m parallel to the shoreline. Keywords: Natural radioactivity, Sediment, Ennore, Gamma ray spectrometry, HPGe detector, Radiological parameters

Naturally occurring radioactive materials (NORM) concentration and health risk assessment of aerosols dust in Nicosia, North Cyprus

This study was carried out to evaluate the distribution of naturally occurring radioactive materials (NORM) and radiological risk indexes in aerosol dust in Nicosia, Cyprus utilizing a high-resolution HPGe gamma-spectrometry. The activity concentrations of 226Ra, 232Th, and 40K in the selected aerosol dust samples ranged from 25.9–52.4, 21.7–46.3, to 471–1302 Bq kg−1, respectively. The average activity concentrations of 40K were found to be above the Earth's crust average. The internal and external hazard indexes are well below the acceptable limit in most dust samples. All investigated samples met the exemption dose limit of 0.3 mSv y−1.

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.

Measuring the radioactivity concentration of 40K, 226Ra, 232Th with PH, conductivity and radiological risk in tap water

ABSTRACT Water is important in environmental studies because of its daily usage by humans and its ability to transport pollutants. The radiological quality of 226Ra, 232Th and 40K in 20 samples of water taps were collected in Kirkuk Governorate, Iraq, and those data have been measured and analysed by gamma ray spectroscopy HPGe detector. The activity concentration of 226Ra ranged from (140.84 to 89.43) mBq.L−1with an average value of 121.95 mBq.L−1, from (106.89 to 47.39) mBq.L−1with an average value of 81.523 mBq.L−1of 232Th, and from (1550.51 to 379.55) mBq.L−1with an average value of 1091.37 mBq.L−1 of 40K, those were lower than the world average values suggested by UNSCEAR: 35, 30, 400 Bq.kg−1. The results show that the values of Raeq varied from (223.24 to 369.90) mBq.kg−1 with a mean of 339.95 mBq.kg−1 which is lower than worldwide average value (370 Bq.kg−1). And the AEDE ranged between minimum and maximum values 120.36 μSvy−1 and 208.33 μSvy−1 with an average value of 186.64 μSvy−1. Also, the values of ELCR ranged from (0.421 to 0.729) × 10−3 with an average value of 0.653 × 10−3, these values were lower than the world’s average value of 3.21 × 10−3. The values of AGDE were ranged from (67.96 to 118.41) μSvy−1 with a mean value of 106.29 μSvy−1 these values were lower than the world average values 300 μSvy−1. Average ingestion of 226Ra, 222Rn 232Th and 40K were found to be 0.6032 μSv y−1 for infants, 0.1141μSv y−1 for children, 0.0350μSv y−1 for adults of 232Th, and 0.57312 μSv y−1 for infants, 7.557 μSv y−1 for children, 3.4146μSv y−1 for adults of 226Ra, also 0.0676 μSv y−1 for infants, 0.0229 μSv y−1 for children, 0.0075 μSv y−1 for adults of 40K. all those values were below the WHO permissible limit of 0.1 mSv y−1 for all ages.

Geochemical Distribution and Environmental Risks of Radionuclides in Soils and Sediments Runoff of a Uranium Mining Area in South China.

Uranium mining activities have contributed to the distribution and uptake of radionuclides, which have increased the active concentrations of natural radionuclides in environmental media, causing elevated human health risks. The present study aims to assess the spatial distribution characteristics of natural radionuclides in the surface soils and river sediments of the typical granite uranium mining area in South China, as well as investigate the geochemical features of natural radionuclides in the soil and sediments to understand their migration processes. The activity concentrations for 238U, 226Ra, 232Th, and 40K ranged from 17-3925 Bq/kg, 50-1180 Bq/kg, 29-459 Bq/kg, and 240-1890 Bq/kg, respectively. The open-pit mining areas and tailings pond locations exhibited the highest concentrations of activity for all these radionuclides. This distribution points to an elevated potential health risk due to radiological exposure in these specific areas. Additionally, the values of radium equivalent activity (Raeq) and annual gonadal dose equivalent (AGDE) in those areas were higher than the limits recommended by ICRP (2021). 238U and 226Ra have a significant correlation (0.724), and the cluster analysis was showing a statistically meaningful cluster below 5 indicated that they have similar behavior during parent rock weathering and watershed erosion, and the distribution of 232Th and 40K were influenced by the addition of rock types. The activity ratios of 226Ra/238U, 226Ra/232Th, 238U/40K, and 226Ra/40K variation indicated that 40K more mobile than 226Ra and 238U, U(VI) was reduced to U(IV) by organic matter in the downstream area and re-entered into the sediment during the sediment surface runoff in the small watershed of the uranium ore open-pit mining area. Therefore, it is necessary to further seal up and repair the tailings landfill area.

Activity concentration and transfer of 226Ra, 232Th, and 40K from soil-to-crops in Irele Local Government Area of Ondo State, Southwestern Nigeria

The activity concentration of radionuclides in soil and crop samples obtained from Irele local government area in Ondo State, Southwestern Nigeria, was evaluated using a 760 mm x 760 mm NaI(Tl) gamma-ray detector system of model 8075, and resolution of 8 % at 0.662 MeV line of 137Cs. In addition, the radionuclide transfer from soil to crops was determined as a result. In soil samples, the mean activity concentrations of 226Ra, 232Th, and 40K were (21.81 ± 3.32, 12.10 ± 4.13, 381.02 ± 11.87Bqkg−1); (31.26 ± 3.98, 15.20 ± 3.82, 357.46 ± 14.62Bqkg−1); (29.81 ± 2.43, 18.86 ± 2.34, 504.25 ± 20.42Bqkg−1) and (27.44 ± 3.07, 21.54 ± 3.61, 449.48 ± 16.14Bqkg−1) corresponding to plantain, maize, yam and cassava, respectively. The mean activity concentration of 226Ra, 232Th, and 40K for plantain, maize, yam and cassava samples are (13.27 ± 4.58, 6.48 ± 3.94, 265.81 ± 13.19Bqkg−1); (27.03 ± 3.70, 10.72 ± 3.07, 345.70 ± 14.63Bqkg−1); (24.03 ± 4.65, 13.79 ± 4.25, 523.53 ± 16.43Bqkg−1) and (21.47 ± 3.57, 14.44 ± 2.20, 432.99 ± 18.56Bqkg−1), respectively. The mean transfer factor values of 226Ra, 232Th and 40K are (0.611, 0.536, 0.700); (0.867, 0.708, 0.967); (0.807, 0.736, 1.040) and (0.785, 0.668, 0.974) for soil-to-plantain, soil-to-maize, soil-to-yam, and soil-to-cassava, respectively. The results revealed that the transfer factor of the crop samples is in the following order: yam>cassava>maize>plantain. The activity concentrations of 226Ra, 232Th, and 40K in the soil and crop samples and corresponding soil-to-crop transfer values did not cause radiation damage to human health as reported levels were below recommended limits. The results of this study may serve as the basis and future criteria for the radionuclide concentrations in soil and their migration factors for the various crops in the study area.

Assessment of radioactivity in sand samples from eastern Nepal in perspective of radiological hazards.

This study was conducted to investigate the activity concentrations of 226Ra, 232Th and 40K in the sand samples and the health hazards associated with them utilizing a NaI (Tl) gamma spectrometer. The average activity concentrations of 226Ra, 232Th and 40K were found to be 24.8±10.1, 39.8±16.4 and 531.3±52.8Bq kg-1, respectively. The calculated radiological hazard parameters, including radium equivalent activity, absorbed gamma dose and effective dose rate, were found to be 122.7±34.0Bq kg-1, 57.7±14.9 nGy h-1 and 0.3±0.1mSv y-1, respectively. Notably, these results were observed to be below the recommended thresholds. Other measured hazard indices were also lower than the prescribed values. From a radiological perspective, the present study concludes that the sand samples do not pose any threat to human health when utilized as a building material.

A preliminary study on determination of radioactivity levels and estimation of the annual effective dose in dried fruits consumed in Albania.

This work aimed to support Albania's food safety monitoring regime. In this context, the natural and artificial radioactivity was measured in 20 samples of dried fruits collected randomly in different markets of Tirana. The activity concentration of 40K, 226Ra, 232Th and 137Cs was determined by using the high-purity germanium detector. The maximum values of activity concentration in dried fruits were calculated as 517±22Bqkg-1 for 40K, 11.10±0.93Bqkg-1 for 226Ra, 4.38±0.26Bqkg-1 for 232Th and 0.83±0.14Bqkg-1 for 137Cs. The average values of activity concentration of 40K and 226Ra were 269and 6.05Bqkg-1 and the average effective dose to individuals from the intake of the dried fruits was 44μSv y-1. All average values in this study were lower than recommended values by reports United Nations Scientific Committee on the Effect of Atomic Radiation, World Health Organization and International Commission on Radiological Protection for all age groups. Therefore, all dried fruit samples in this study are safe for consumption with acceptable radiological risk and none of them pose any significant radiological impact. The obtained data in this paper and information for levels of radioactivity and ingestion absorbed dose from dried fruits can be used to be the basic data for future comparative analysis of the other studies.

Assessment of natural radioactivity in soil and olive mill pomace utilizing nal (TI) gamma-ray spectrometry and low background alpha/beta counting system

The study conducted in the northwest region of Jordan aimed to assess the levels of natural radioactivity in soil and olive mill pomace (OMP) samples. The researchers used Nal (TI) gamma-ray spectrometry to measure the activity concentrations of 226Ra, 232Th, 40K, and 137Cs in the samples. The average activity concentrations of 226Ra, 232Th, 40K, and 137Cs in the soil samples were found to be 18.624 ± 5.82, 12.276 ± 5.728, 518.33 ± 212.57, and 0.140 ± 0.09 (Bq,kg−1), respectively. In the OMP samples, the average activity concentrations of 226Ra, 232Th, and 40K were 7.272 ± 4.386, 3.454 ± 1.503, and 169.997 ± 81.873 (Bqkg−1), respectively, and no 137Cs was detected.The study also investigated fundamental parameters associated with radon, specifically the radon emanation coefficient (RnEC) and radon mass exhalation rate (Ex). The RnEC values ranged from 0.621 to 0.78 (Bqkg−1), with an average value of 0.71 ± 0.06 (Bqkg−1). The estimated Ex from the soil samples ranged from 65.83 to 124.86 (mBqkg−1h−1), with an average value of 99.74 ± 21.73 (mBqkg−1h−1).Regarding radiological hazards, the study examined various parameters, including radium equivalent activity, external and internal hazard indices, gamma and alpha indices, absorbed gamma dose rate, and excess lifetime cancer risk. All of these assessed values were found to be below the worldwide recommended limits for radiological safety.Additionally, the study analyzed the concentrations of gross alpha and gross beta radioactivities in soil and OMP samples. The soil samples had an average gross alpha activity of 4.642 ± 1.04 (Bqkg−1) and an average gross beta activity of 48.13 ± 14.50 (Bqkg−1). The OMP samples showed an average gross alpha activity of 0.32 ± 0.27 (Bqkg−1) and an average gross beta activity of 59.19 ± 12.94 (Bqkg−1).Overall, the obtained results are crucial for evaluating the radiological risks associated with natural radioactivity in the northwest region of Jordan. The findings establish baseline data for comparison and reference for radioactivity levels in the environment.

A Study on Determination of Natural Radionuclide Concentrations in Tap Water Samples Collected from the Districts of Sinop Province, Türkiye

Since Turkey's second nuclear power plant is planned to be built in Sinop province, it is very important to determine the background levels of radioactivity in this region. In the present study, activity concentrations of 226Ra, 232Th and 40K natural radionuclides in nine tap water samples collected from the districts of Sinop province located in the north of Turkey were determined using a high purity germanium detector (HPGe). The coordinates of sampling areas were also recorded by GPS device (Magellan Explorist 510). The mean activity concentrations of 226Ra, 232Th and 40K radionuclides in the studied waters were calculated to be 1.74 ± 0.49 Bq/L, 1.39 ± 0.35 Bq/L and 5.32 ± 1.41 Bq/L. In addition, annual effective dose equivalents from the intake of these radionuclides in the tap water samples were calculated for infants, children and adults and the found results were compared with the values recommended by international organizations. As a result, there is no risk in terms of natural radioactivity in the consumption of studied waters by humans.

MEASUREMENT OF NATURAL RADIOACTIVITY IN TAP WATER SAMPLES FOR SELECTED REGIONS IN ADEN GOVERNORATE, YEMEN

In the present work, we have measured specific activity concentrations of in eleven tap water samples for selected regions in Aden governorate by using high purity germanium detector (HPGe). The (HPGe) detector (CANBERA-model 7229N, USA) with an efficiency of 35% and energy resolution (2.6keV) at energy (1332.6keV) for 60Co, the high purity N-type semiconductor detector with physical characteristics of (geometry closed-end coaxial, (3×3 inch). The results have shown that, The highest value of specific activity concentration of 226Ra was found in in T7 Daar-Saad region which was equal to (0.525±0.29)Bq/L, while the lowest value of specific activity concentration of 226Ra was found in T11 Aden Assughra region which was equal to (0.017±0.006)Bq/L with an average value of (0.228±0.13)Bq/L. The highest value of specific activity concentration of 232Th was found in in T5 Khor-makser region which was equal to (0.319±0.18)Bq/L, while the lowest value of specific activity concentration of 232Th was found in T11 Aden Assughra region which was equal to (0.009±0.001)Bq/L with an average values of (0.129±0.089)Bq/L. The highest value of specific activity concentration of (40K) was found in in T2 (Al-Ma,allah) region which was equal to (0.4±0.26)Bq/L, while the lowest value of specific activity concentration of (40K) was found in T11 Aden Assughra region which was equal to (0.027±0.004)Bq/L with an average values of (0.141±0.021)Bq/L respectively. The annual ingestion effective dose (AED) ranged from (3.05 to 98.77μSv/y), (5.67 to 178.16μSv/y), and (3.41 to 119.08μSv/y), with average values of 42.65μSv/y, 78.62μSv/y and 48.62μSv/y, for infants, children and adults respectively. The excess lifetime cancer risk (ELCR) have been calculated, its values were lower than the world’s average value of (0.29×10−3) as reported by EPA. The overall annual effective dose and cancer risks corresponding to radionuclide intake in tap water were below the recommended maximum values. It was inferred from the findings of this study that the water used as the sample does not have any significant radiological impacts to human body and is safe to be used as drinking water.

Estimation of Radiation Dose in Building Materials Used In Federal University Gusau Using Gamma-Ray Spectroscopy Analysis

This study estimated the radiation dose in building materials (sand, cement, and granite) in Federal University Gusau, Zamfara State, Nigeria, through gamma-ray spectrometry system using a Sodium Iodide Thallium activated "NaITl" detector in a low background configuration. The range of the average activity concentration of 226Ra was found to be 56.65±0.75Bqkg-1 to 159.45±2.68Bqkg-1, which was higher than that of the world mean value for soil 35Bqkg-1,for 232Th the range was 46.65±0.45Bqkg-1 to 79.32±1.68Bqkg-1, all the samples, were found to be higher than that of the world mean for soil 30Bqkg-1. While the activity concentrations of 232Th levels of blocks, granite, and sand samples are all above the world range, except the cement which was within the worldwide range 194.84±1.31Bqkg-1 to 656.84±0.76Bqkg-1. The average activity concentration of 40K for cement, sand, and blocks was within the worldwide range, with granite samples slightly higher than the world mean value for soil 400Bqkg-1. The results have been compared with the world mean values of 35, 30, and 400Bqkg-1 specified by the UNSCEAR (2016). Concerning radiological risk to human health, the absorbed gamma dose rate (D) was estimated to be above the world average range of 55nGyh-1; the outdoor annual effective dose equivalent (AEDE) were, estimated to be below the permissible limit of 0.07mSvy-1. The values of Raeq, Hex, and Hin for all the samples in the present work are lower than the accepted safety limit value of 370Bqkg-1 and below the limit of unity, respectively.