Search

Argillic alteration and hematitization are the two extensive alterations that affected Um Safi rhyolite flow tuffs. Rare metal mineralization including radioactive minerals (thorite, uranothorite), Nb-bearing minerals (columbite, yettrocolumbite, Nb-rutile), zircon, REE-minerals (LREE-carbonate, xenotime) as well as molybdite, pyrite, fluorite, hematite and ilmenite have been identified by using Energy Dispersive Spectrometer (EDS) and are well recorded in argillic and hematitized samples. The investigated rhyolite flow tuffs show that the activity concentration of radionuclides changed from 1.2 to 453.2 Bq kg−1 for 238U, from 3.2 to 489.6 Bq kg−1 for 232Th, and from 31.3 to 88954.6 Bq kg−1 for 40K. The mean values of 238U, 232Th, and 40K activity concentrations are 90.8 ± 84.5, 122.9 ± 90.5 and 6286.7 ± 1562.2 Bq kg−1, respectively. The hazard factors are estimated. Their results exceeded the recommended limit. Thus, the investigated rhyolite flow tuffs are not safe to use in building materials and other construction industries. A multi-statistical approach is performed to show the correlation between the radioactive concentration and radiological hazard factors. This approach illustrates the positive correlation between uranium and thorium due to their contribution from the natural radioactive series—moreover, a strong correlation was obtained between potassium and all radiological parameters. Thus, the radioactive hazards impact in the present study is related to the presence of radioactive minerals such as thorite and uranothorite in addition to other accessory minerals. • Rhyolites and their tuffs represent an economic strategy to apply in various building materials. • The radioactivity is detected in the granitic rocks samples using GR-320 spectrometer. • The radioactive hazards parameters are computed, and the risk of the hazard is assessed. • The emitted radiation of Rhyolites and their tuffs at the studied area poses significant health risks. [ABSTRACT FROM AUTHOR]

In this study, the human health risks of potentially harmful elements (PHEs) in urban surface deposited sediments (USDS) were examined by collecting urban dust samples, measuring their PHE concentrations, and using index evaluation. About 35, 12 and 16 samples are represented a green zones, roads, driveways and sidewalks in residential areas of Ekaterinburg, respectively. The dust fraction (0.002–0.1 mm) was obtained by sieving, filtration, and decantation process. Total concentrations of 10 PHEs were measured using inductively coupled plasma mass spectrometry. The highest concentrations of Pb were found in USDS from green zones, while Fe, V, Mn, Co, Ni, Sn, and Sb on roads, Cu and Zn on driveways and sidewalks. The contamination levels in the investigated land-use areas were studied, where the highest contamination was contributed from Sb in the driveways and sidewalk. Moreover, the pollution in the studied zones was a high load, contributing to anthropogenic activities and traffic emissions. No non-cancerogenic risk was attributed from the PHEs based on the results of health indices (HI < 1) for both adult and children, except Co and Ni which has HI > 1 for children. The total carcinogenic risk (TLCR) in all urban landscape areas is defined as a high potential inhalation exposure and a low potential ingestion and dermal exposure. [Display omitted] • The health risk associated with the toxic metals in urban surface sediments is studied. • The inhalation contributes about 99% of total risk due to USDS. • The total lifetime cancer risk is below 10−3. • High cancerogenic risk is produced due to the Co element in urban surface sediments. [ABSTRACT FROM AUTHOR]

Assessment of the radioactive impacts of building materials has become important before materials are employed in various infrastructure fields. The current study conducted a radiological survey on multiple granitoids in the Nikeiba area, southeastern Desert, Egypt. The petrographically studies were performed and illustrated the presence of radioactive bearing minerals in the investigated granitoids. The activity concentrations of 238U, 232Th, and 40K in these rocks, including the granitoids, are measured using a GS-256 spectrometer with a 0.35 L sodium iodide (NaI) thallium activated detector. The activity concentration of 238U, 232Th, and 40K varied from 1 ± 0.3, 4 ± 1 and 94 ± 15 Bq kg−1 to 274 ± 74, 229 ± 24, and 3537 ± 436 Bq kg−1 with the mean value of 83 ± 47, 104 ± 50 and 1140 ± 462 Bq kg−1, respectively. Multivariate statistical analysis is applied to detect the correlation and similarities of radionuclides with the radioactive hazard indices. Pearson correlation analysis depicts the distribution of 232Th controls the distribution of 238U in the granitoids. The primary radiological health hazard characteristics related to the concentrations of 238U and 232Th were determined by the variance of 89.76% derived using PCA. The cluster analysis dendrogram results indicate a good match with the correlation analysis. • Natural radioactivity characterization of granitoids in the studied area, Egypt, was performed. • Radiological hazard indices were computed, and the risk assessment was assessed. • The emitted radiation of granitoids at Neikeiba area poses significant health risks. [ABSTRACT FROM AUTHOR]

The present work aims to study gamma rays emitted by radionuclides such as 238U, 232Th and 40K from acidic Monqul volcanics. The studied volcanics are represented by a thick stratified lava flows interbanded with their pyroclastics. They are composed of thick lava flows of andesite and, to a lesser extent of basalt, and acidic volcanics including rhyolite and dacite. The average values of 238U, 232Th and 40K are (46 ± 24 Bq kg-1), (62 ± 11 Bq kg-1) and (1227 ± 318 Bq kg-1) in the rhyolite-dacite samples are greater than the worldwide average. The variation of radioactive bearing minerals observed inside granite faults produced the great amounts of radioactivity perceived in the samples. Calculating radiological risks is used to assess the public's radioactive risk from radionuclides revealed in the studied Rhyolite-dacite samples. The acceptable limit for excess lifetime cancer (ELCR) evaluations has been exceeded. As a result, Rhyolite-dacite are inappropriate for apply in building materials. • Rhyolite and dacite represent an economic strategy to apply in various building materials in Egypt. • A calibrated gamma-ray spectrometer is used to measure radioactivity in rhyolite and dacite samples. • The radioactive hazards parameters are calculated, and the hazard's risk is evaluated. • The rhyolite and dacite released radiation in the Monqul area poses a serious health concern. [ABSTRACT FROM AUTHOR]

Stream sediment is a useful raw material used for building construction, mostly used in the desert parts of the world. Such sediment is a Naturally Occurring Radioactive Material (NORM), and, hence, it requires a radiological characterization to be used. This work aims to study the natural radioactivity in fifty points distributed in surface of stream sediments in the area of Gabal El Seila region, south-eastern desert of Egypt, since there is a lack of information about the radioactivity levels of the sediment samples from such recent growing interest area. The activity concentration of 238U, 232Th and 4 K natural radionuclides using a portable RS-230 γ-ray spectrometer were determined. Mean values are 38.51 ± 10.83, 33.35 ± 8.82, 659.18 ± 110.87 Bq/kg for 238U, 232Th, 4 K respectively. Radiological hazard indexes were computed and compared with the UNSCEAR and other worldwide ranges. All the results are statistically presented and discussed. They show that no significant radiation hazard coming from the studied area, with the most values lower than international recommended limits. The achievements of the present study fall within the measurements of natural environmental radiation in an unexplored area of great interest being a desert. The obtained results can be used as database for future research, and as tool for radiological awareness in the use of sediments as raw material. • Natural radioactivity characterization of Gabal El Seila region - Egypt, was carried out. • Radiological hazard indexes were computed to evaluate the human risk assessment. • 232Th/238U ratio showed 20% higher and 80% lower values than worldwide average value. • No significant natural radiation hazard comes from the region, lower than recommended levels. [ABSTRACT FROM AUTHOR]

Mercury is a toxic environmental element, so it was necessary to prepare a new, highly efficient, cheap sorbent to remove it. A mesoporous thioacetamide/chitosan (MTA/CS) was manufactured via a simplistic strategy; the chitin deacetylation to gain chitosan (CS) and the addition of thioacetamide. The as-prepared MTA/CS was characterized using X-ray diffraction, EDX, SEM, FTIR, and BET surface analysis. According to the findings, the MTA/CS was effectively synthesized. The removal behaviors of Hg2+ onto MTA/CS composite were inspected, which suggested that the MTA/CS composite exhibited great sorption properties for Hg2+ in liquid solutions. The maximal Hg2+ sorption capacity was 195 mg/g. The effects of temperature, Hg2+ concentration, contacting time, and MTA/CS concentration on sorption were analyzed. The 2nd-order model and Langmuir isotherm were suitable for the physicochemical adsorption processes. Thermodynamic analysis showed that the Hg2+ adsorption process onto the MTA/CS composite is exothermic and occurred spontaneously. The desorption condition of Hg2+ from its loaded MTA/CS was also gained. Likewise, the MTA/CS sorbent was undoubtedly regenerated by 0.8 M NaNO 3 80 min contacting and 1:50 S:L ratio. The versatility and durability of MTA/CS sorbent were investigated via nine sorption-extraction cycles. The optimum parameters were applied to wastewater. Based on the result, the as-prepared MTA/CS might be a potential sorbent for removing Hg2+ from liquid solutions. [Display omitted] • Chitosan can be functionalized by thioacetamide to prepare thioacetamide/chitosan (MTS/CS). • Thioacetamide/chitosan has high affinity to absorb Hg2+ ions from wastewater. • The maximum sorption capacity of Hg2+ on MTA/CS is 195 mg/g. • The sorption process implies the 2nd-order model and Langmuir isotherm. • The desorption of Hg2+ ions is conducted by 0.8 M NaNO 3 , 80 min, and 1:50 S:L ratio. [ABSTRACT FROM AUTHOR]

One of the most well-liked energizing drinks is now tea, which is primarily used in Malaysia. The natural radioactivity in the associated soils where tea plants are cultivated plays a major role in determining the presence of radionuclides in tea leaves. The present study assesses the transfer of radionuclides from soil-to-tea leaves and then estimates the committed effective doses through tea consumption. Tea leaves and the associated soils were obtained from the largest tea plantation area, which is located in the Cameron Highlands, Malaysia. The marketed tea leaves in powdered form were obtained from the supermarkets in Kuala Lumpur. HPGe gamma-ray spectrometry was used to determine the prevailing concentrations of long-lived radioactive materials in tea leaves. Activity concentrations of 226Ra, 232Th, and 40K in tea soils ranged from 49 to 101.7 Bq kg−1, 74.5–124.1 Bq kg−1 and 79.6–423.2 Bq kg−1, respectively, while the respective values in tea leaves are 14.4–23.8 Bq kg−1, 12.9–29.5 Bq kg−1 and 297–387.5 Bq kg−1. Transfer factors of radionuclides showed typical values (<1.0) except for the 40K. The threshold tea consumption rates suggest that one should not consume more than 67 g of tea leaves per day (around 4 g of tea leaves are needed for making 1 cup of tea, so 17 cups per day) to avoid negative health effects. Committed effective doses due to tea consumption are found to be lower (5.18–6.08 μSv y−1) than the United Nations Scientific Committee on the Effects of Atomic Radiation (2000) reference dose guidance limit of 290 μSv y−1 for foodstuffs; however, it should be noted that the guidance limit is recommended for all foodstuffs collectively. Providing data on natural radioactivity in tea leaves grown in Malaysia, this study may help people manage a healthy lifestyle. • Radionuclides transfer from soil-to-tea leaves and associated doses are studied. • Tea leaves are collected from the largest tea estate in Malaysia. • Radioactivity in tea leaves are reported for the first time in Malaysia. • Committed effective dose found below the UNSCEAR guidance limit of 290 μSv y−1. • The reported data may be useful to maintain a healthy lifestyle. [ABSTRACT FROM AUTHOR]

In clinical settings, standard dosimeters might miss radiation mishaps. Retrospective dosimeters could help to track personnel (such as patients and other staff who don't wear dosimeters) exceeding safe limits and assess long-term exposure trends. This study has investigated key thermoluminescence (TL) dosimetric characteristics, including the glow curve structure, dose-response, energy dependence, sensitivity and fading of various safety glasses that are used as screen protectors of smartphones subjected to photon irradiation. Among the studied glasses, the HD Anti-Peep safety glass for iPhone has been found to exhibit a linear dose-response with a regression coefficient of 99% within the dose range of 2–10 Gy. Moreover, all the safety glasses showed independence with respect to photon energy of 6 MV and 10 MV. The TL glow curves of the samples showed a broad glow peak between 125 °C and 325 °C at 10 Gy. The TL kinetic parameters of the safety glasses were also studied by analyzing the glow curves using the peak shape and initial rise method. The geometric factor (μ g) is found to be within the range of 0.43–0.53, which indicates the suitability of applying Chen's general-order formula to calculate the kinetic parameters such as activation energy, frequency factor and trap lifetime. The activation energy (E) and frequency factor (s) are found in the range of 0.31–0.54 eV and 4.55 × 103 to 2.12 × 106 s−1 respectively obtained via the peak shape method. The relatively long trap lifetime and observed thermoluminescence features indicate that the HD Anti-Peep safety glass offers a better option to estimate dose retrospectively to ensure the safety of human health. • TL properties of smartphone safety glasses in the photon dose range of 2–10 Gy are studied. • Kinetic parameters of safety glasses in the photon energy of 6 and 10 MV are studied for the first time. • Smartphone safety glass, HD Anti-Peep exhibits favorable TL features for retrospective dosimetry. [ABSTRACT FROM AUTHOR]

The study evaluated the structural and thermoluminescence (TL) kinetic parameters of smartphone screen protector glasses in order to use them for post-accident dose reconstruction from unplanned nuclear events. The fact that most individuals use mobile phones in working environments including nuclear power plant sites, served as the impetus for the study. The TL glow curves indicate the physical properties of the defects involved in the luminescence process; therefore, they have been analyzed to study the TL kinetic parameters by employing peak shape, initial rise and glow curve deconvolution method within the dose ranges from 2 to 50 Gy. The geometric factor (μg) ranges between 0.46 and 0.56, suggesting that Chen's general-order method can be used to compute the kinetic parameters, including activation energy (E), frequency factor (s) and trap lifetime (τ). The examined trapping parameters (E = 0.33–0.57 eV, s = 5.22E+03–8.65E+06 s−1 for peak shape and E = 0.36–0.96 eV, s = 2.90E+04–1.88E+11 s−1 for initial rise methods) suggest promise for TL dosimetry applications. Additionally, the observed lifetime (τ = 4.88E+5 s) implies the feasibility of dose reconstruction even several days after an accident, making it suitable for retrospective dosimetry. Micro-Raman spectroscopy revealed a clear correlation between increasing gamma radiation dose and microstructural damage. The analysis of intensity ratio (I D /I Si) for other components to silica, along with the area of deconvoluted micro-Raman spectra in high-frequency regions, indicated dose-dependent structural modifications and internal defect annealing. Further confirmation of structural alterations within the studied dose range was obtained through the analysis of crystallite size (L c), dislocation density (δ), lattice strain (ɛ) and FWHM (Full Width at Half Maximum) from XRD (X-ray diffraction) patterns. These findings collectively suggest the potential of smartphone screen protector glass as a viable material for emergency dosimetry applications. • This study explores the potential of smartphone screen protector glasses for dose reconstruction after nuclear accidents. • Thermoluminescence analysis reveals promising kinetic parameters for traditional dosimetry applications. • Observed trap lifetimes suggest suitability for retrospective dosimetry, allowing dose reconstruction even after long time. • Analysis of structural parameters confirms dose dependence, further supporting for emergency dosimetry. [ABSTRACT FROM AUTHOR]

Globally, the use of nuclear facilities and the potential risks associated with the dispersal of ionizing radiation due to natural disasters or technical failures are on the rise. These risks can have severe consequences for the environment and all living organisms, particularly humans. There is currently no practical method available to accurately estimate the radiation doses received by the surrounding areas and individuals in such situations. To address this issue, retrospective dosimetry can be employed to estimate the actual radiation dose, followed by the implementation of remediation techniques. Considering this need, tempered glass, which is commonly used as a screen protector for smartphones by the general public, has been identified as a promising medium for retrospective dosimetry. The present study aimed to investigate the thermoluminescence (TL) properties of six different types of tempered glass subjected to 60Co gamma rays, specifically examining the TL dose response, linearity, repeatability, and fading. Among the various glass samples tested, HD anti-peep tempered glass demonstrates a highly linear dose-response and the greatest dose sensitivity within the examined dose range of 2–50 Gy. Additionally, the HD anti-peep tempered glass exhibits minimal loss of TL yield (∼23%) at 28 days post-irradiation, making it particularly suitable for use as a retrospective dosimeter. • First-study of TL properties of tempered glass for retrospective dosimetry in the dose range of 2–50 Gy. • Commercially available Tempered glasses are studied for radiation dosimetry. • Use was made of TL and SEM-EDX techniques to characterize the samples. • HD anti-peep tempered glass exhibits favorable TL features for retrospective dosimetry. [ABSTRACT FROM AUTHOR]

Spiral computed tomography (CT) scans, which are considered a high-contrast resolution, quick and cross-sectional imaging technique, have grown in popularity as a result of technological advancements. However, these advancements have brought with them the potential for significantly increased radiation doses to the patient. Consequently, many organizations recommended optimization and establishing diagnostic reference levels. The aim of the current study was to assess CT radiation dose and propose a local diagnostic reference level (LDRL) for the adult trunk [chest and abdomen] using CT dose parameters such as CT dose index volume (CTDI vol) and dose length product (DLP) as well as to compare the practices for aforementioned examinations between two hospitals in Taif and Abha cities in Saudi Arabia. Data from 428 patients (216 for abdomen and 212 for chest) who were examined in two hospitals in Taif and Abha City in Saudi Arabia from December 2022 to March 2023, are used in this study. The data for hospitals in Taif and Abha are presented as 'T' and 'A' throughout this manuscript. The parameters of exposure and slice thickness were recorded in a specially designed data sheet together with the gender, age and patients morphometric. Microsoft Excel version 2010 was used to analyze results and plot the figures. The LDRL was achieved from the third quartile of CTDIvol and DLP for each hospital and examination. The average DLP (mGy-cm) and CTDI vol (mGy) for the chest and abdomen were 243 mGy cm, 5.8 mGy and 549 mGy cm, 8.6 mGy respectively. The average effective dose (ED) for chest and abdomen were 5.10 and 21.10 mSv, respectively. The proposed LDRL for the chest and abdomen were 6.9 mGy (CTDIvol), 375 mGy-cm (DLP), 7.8 mGy (CTDIvol), and 747 (DLP) mGy-cm, respectively. Hospital 'A' irradiated patients with a higher dose for the abdomen exam than Hospital 'T', but both hospitals agreed on the amount of radiation dose received by patients for chest imaging. The proposed LDRL for two examinations was less than the DRL obtained from the literature. • Computed Tomography radiation doses for the chest and abdomen were assessed. • 428 adult patients who underwent chest and abdomen CT exams were examined. • Average effective dose for chest and abdomen were 5.10 and 21.10 mSv, respectively. • Suggested local diagnostic reference level was lower than the previous studies. [ABSTRACT FROM AUTHOR]

The present study aims to evaluate the possibility of constructing a new high-speed railway (HSR) at Al Sādis Min Uktōber city, Cairo (Egypt): geotechnical and environmental radiological hazards are estimated from several collected soil and water samples. A variety of laboratory geotechnical tests such as grain size, free swelling test, liquid and plastic limits, chemical analysis and uniaxial compression strength are applied to sixty-one drill holes. A geotechnical examination of the coarse-grained soil at the foundation level classified it as poorly graded soil. The results of the investigation of fine-grained soil at the foundation level shown that the liquid limit ranges from 22% to 55%, the plastic limit ranges from 12% to 28%, the plasticity index varies from 11% to 33%, free swelling varies from 51% to 71%. Mechanically, the uniaxial compressive strength values on rock samples range from 6.96 MPa to 142.39 MPa. The radioactive study is performed to detect the 226Ra, 232Th, and 40 K activity concentrations of the soil samples: their mean values are 34 ± 10 Bq·kg−1, 14 ± 5 Bq·kg−1 and 552 ± 20 Bq·kg−1, respectively. The values of radiological hazard indexes are not exceeded the permissible limits: e.g. the mean value of absorbed dose rate is 47 ± 6 nGy h−1; the annual gonadal dose equivalent is 0.3 ± 0.04 mSv·y−1; the lifetime cancer risk is 02 ± 0.2·10−3. Thus, the soil in the studied railway area is safe to use in building materials and infrastructure applications: the radiological hazards and the geotechnical studies confirmed the studied area is suitable to construct a new community having a HSR. According to the SWOT-PEST and environmental impact analyses, the construction of the HSR meets the criteria of the Kyoto Protocol, the EU Climate and Energy policy, and other international treaties. • Study at Al Sādis Min Uktōber city, Egypt, for high-speed railway construction. • The values of radiological hazard indexes are not exceeded the permissible limits. • SWOT-PEST and environmental impact analyses meet the criteria of the Kyoto Protocol. • Geotechnical examination at foundation show poorly graded soils. [ABSTRACT FROM AUTHOR]

The intensification and adsorption of uranium on different adsorbents are considered an operative substitute technique for extraction from nuclear effluent. Many synthetic adsorbent materials have recently been developed for the removal of uranium from aqueous solution. Latterly, clay is a fundamental adsorbent to be considered in uranium recovery owing to the promising sorption properties. In this study, a spent bleaching earth from an edible oil manufacturing was remedied with a view to get rid of the edible oil remnants and then steeped in β‒naphthol to promote its adsorption characteristics. The clay is characterized by X‒ray Fluorescence (XRF), Fourier Transform Infrared Spectrometer (FTIR), surface area analyzer, Scanning Electron Microscope (SEM), and Energy-dispersive X‒ray spectroscopy (EDX). The experiments have been conducted upon adsorption efficiency of uranium to optimize the influence of pH value, agitation time, clay dosage, initial uranium ions concentration, and system temperature The uptake capacity of the new adsorbent is 175.10 mg g−1; it was been attained at pH 4.5, 60 min, and 25 °C. Both of the kinetic and isotherm of adsorption process were calculated and the data work in with pseudo‒first‒order kinetic model along with Langmuir‒Freundlich isotherm. Furthermore, the thermodynamic study implies the spontaneousness and exothermicity of the adsorption process of uranium ions. The negative value of ΔS° refers to the practicality of adsorption of uranium ions and the mitigation in randomness for the new adsorbent clay. • Preparation and characterisation of regenerated bleaching earth steeped in β‒naphthol (RBESN). • Uranium ions are adsorbed on RBESN. • The maximum uptake capacity is 175.10 mg g−1. • Uranium elution is attained by 1.0 M conc of H 2 SO 4 , 75 min, and 1:50 S:L ratio at 25 °C. • The elution effectiveness was reduced from 98.0 to 82.0% after 9 succeeding rounds. [ABSTRACT FROM AUTHOR]