Uranium Concentration In Samples Research Articles

Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid: A Case Study in a Nuclear Fuel Fabrication Plant.

Inhalation exposure to uranium aerosols can be a concern in nuclear fuel fabrication. The ICRP provides default absorption parameters for various uranium compounds but also recommends determination of material-specific absorption parameters to improve dose calculations for individuals exposed to airborne radioactivity. Aerosol particle size influences internal dosimetry calculations in two potentially significant ways: the efficiency of particle deposition in the various regions of the respiratory tract is dependent on aerodynamic particle size, and the dissolution rate of deposited materials can vary according to particle size, shape, and porosity because smaller particles tend to have higher surface-to-volume ratios than larger particles. However, the ICRP model assumes that deposited particles of a given material dissolve at the same rate regardless of size and that uptake to blood of dissolved material normally occurs instantaneously in all parts of the lung (except the anterior portion of the nasal region, where zero absorption is assumed). In the present work, the effect of particle size on dissolution in simulated lung fluid was studied for uranium aerosols collected at the plant, and its influence on internal dosimetry calculations was evaluated. Size fractionated uranium aerosols were sampled at a nuclear fuel fabrication plant using portable cascade impactors. Absorption parameters, describing dissolution of material according to the ICRP Human Respiratory Tract Model, were determined in vitro for different size fractions using simulated lung fluid. Samples were collected at 16 time-points over a 100-d period. Uranium content of samples was determined using inductively coupled plasma mass spectrometry and alpha spectrometry. In addition, supplementary experiments to study the effect of pH drift and uranium adsorption on filter holders were conducted as they could potentially influence the derived absorption parameters. The undissolved fraction over time was observed to vary with impaction stage cut-point at the four main workshops at the plant. A larger fraction of the particle activity tended to dissolve for small cut-points, but exceptions were noted. Absorption parameters (rapid fraction, rapid rate, and slow rate), derived from the undissolved fraction over time, were generally in fair agreement with the ICRP default recommendations for uranium compounds. Differences in absorption parameters were noted across the four main workshops at the plant (i.e., where the aerosol characteristics are expected to vary). The pelletizing workshop was associated with the most insoluble material and the conversion workshop with the most soluble material. The correlation between derived lung absorption parameters and aerodynamic particle size (impactor stage cut-point) was weak. For example, the mean absorption parameters derived from impaction stages with low (taken to be <5 μm) and large (≥5 μm) cut-points did not differ significantly. Drift of pH and adsorption on filter holders appeared to be of secondary importance, but it was found that particle leakage can occur. Undissolved fractions and to some degree derived lung absorption parameters were observed to vary depending on the aerodynamic size fraction studied, suggesting that size fractionation (e.g., using cascade impactors) is appropriate prior to conducting in vitro dissolution rate experiments. The 0.01-0.02 μm and 1-2 μm size ranges are of particular interest as they correspond to alveolar deposition maxima in the Human Respiratory Tract Model (HRTM). In the present work, however, the dependency on aerodynamic size appeared to be of minor importance, but it cannot be ruled out that particle bounce obscured the results for late impaction stages. In addition, it was noted that the time over which simulated lung fluid samples are collected (100 d in our case) influences the curve-fitting procedure used to determine the lung absorption parameters, in particular the slow rate that increased if fewer samples were considered.

ОСОБЛИВОСТІ ЛОКАЛІЗАЦІЇ УРАНОВОГО ЗРУДЕНІННЯ В МЕЖАХ ТЕРЕЙНУ ТАЗІАСТ-ТІДЖІРІТ, РЕГІБАТСЬКИЙ ЩИТ

The Reguibat Shield is an area of intensive uranium exploration and about 80 ore occurrences have been discovered in recent decades within its borders. The region of the study is located within the Tasiast-Tijirit terrane, which represents a northwestern part of Archean domain of the Reguibat Shield. The rocks of the terrane are of Mesoarchean age. The main types of rocks are migmatites, gneisses and amphibolites, greenstone associations, granitic intrusions and pegmatites. Samples of pegmatites, granites, ferruginous quartzites and sedimentary rocks that showed an increased radiation level after conducting a ground-based radiometric survey were selected for laboratory studies from the host rocks of the Tasiast-Tijirit terrane. The following types of laboratory analyses were used for the study: 1) spectral analysis by laser-luminescence method to determine the uranium content in samples; 2) atomic emission spectroscopy for the general estimation of concentrations of chemical elements in samples; 3) X-ray fluorescence analysis to determine the chemical composition of samples and its trace elements; 4) electron microprobe analysis to determine the morphology of mineralization and the chemical composition of uranium minerals. Among the Tasiast-Tijirit terrane rocks the increased uranium content was found in the following rock associations: pegmatites and granites; ferruginous quartzites within the banded iron formation; calcretes in sedimentary rocks. According to the results of field and laboratory studies, the main factors of the localization of uranium mineralization in calcretes of the OumDherua area were established. The main geological, physical and chemical conditions essential for the formation of uranium mineralization of the calcrete type within the study region were established. It was found that granites and pegmatites could provide source of uranium for ore mineralization in sedimentary formations, such as surficial and calcrete types. The latter are studied and mined quite intensively in the world including the Reguibat Shield. The study results show the high potential for prospecting and exploration of new uranium occurrences within the Tasiast-Tijirit terrane.

ВЛИЯНИЕ ГЕОЛОГИЧЕСКИХ ФАКТОРОВ НА РАСПРЕДЕЛЕНИЕ УРАНА И ТОРИЯ В СОЛЕВЫХ ОТЛОЖЕНИЯХ ПИТЬЕВЫХ ВОД (РЕСПУБЛИКА БАШКОРТОСТАН)

Актуальность исследования обусловлена необходимостью выявления источников поступления естественных радиоактивных элементов в питьевую воду,а также возможностью использования солевых отложений питьевых вод (накипи) в геохимических и экологических исследованиях. Наличие на территории Башкортостана различных геологических структур (горная область, предгорный прогиб, платформа), а также большое разнообразие горных пород различного возраста и состава (вулканогенные, интрузивные, осадочные, метаморфические) благоприятствует данным исследованиям и обуславливает большое разнообразие микроэлементного профиля местности. Цель:оценка содержания и пространственного распределения радиоактивных элементов в солевых отложениях питьевых вод (накипи) на территории Республики Башкортостан. Объекты. Проанализированы данные по содержанию U и Th в 467 пробах солевых отложений питьевых вод (накипи) из 267 населенных пунктов Республики Башкортостан. Пробы отобраны из различной посуды (эмалированные и электрические чайники, кастрюли, котлы, самовары), которая используется для кипячения воды из централизованных и индивидуальных (скважины, колодцы, ручьи) источников водоснабжения. Методы. Для анализа содержания Uи Thиспользовался метод инструментального нейтронно-активационного анализана базе исследовательского ядерного реактора ИРТ-Т ТПУ. Обработка данных проводилась с использованием программных пакетов Statistica 8.0 и MicrosoftExcel 2013. Построение карт пространственного распределения естественных радиоактивных элементов в солевых отложениях питьевых вод проведено с помощью программы ArcGIS 10.2 в модуле GeostatisticalAnalyst методом обратных расстояний. Результаты. Полученные данные позволяют говорить о неравномерном распределении естественных радиоактивных элементов (U, Th) в солевых отложениях на территории Республики Башкортостан. Региональный фон концентрацииU и Th отличается пониженными значениями. Вариации их содержания определяются воздействием как природных, так и антропогенных факторов. Закономерности распределения U в пробах накипи хорошо согласуются с особенностями геологического строения территории. В пределах платформенной части распределение Uявляется более равномерным по площади, чем в горной части республики, что отражает сравнительную однородность геологических и тектонических условий. По результатам картирования выделено четыре зоны повышенного содержания Uв образцах солевых отложений: зауральская, уральская, западная и южная.В пространственном распределении Th не выявлено четкой корреляционной связи с особенностями геологического строения и металлогении территории. Выделены три зоны: северная, центральная и юго-восточная. Отмечены отрицательные аномалии содержания Th, территориально совпадающие с крупными горнодобывающими центрами.Показатель Th/U отношения характеризуется низким значением для всей территории Башкортостана – 0,002. При этом положительные аномалии данного показателя зафиксированы в северной и юго-восточной частях республики, где они обусловлены, преимущественно, геологической составляющей.

Comparison of solvent extraction and extraction chromatography resin techniques for uranium isotopic characterization in high-level radioactive waste and barrier materials

The development of Deep Geological Repositories (DGP) to the storage of high-level radioactive waste (HLRW) is mainly focused in systems of multiple barriers based on the use of clays, and particularly bentonites, as natural and engineered barriers in nuclear waste isolation due to their remarkable properties.Due to the fact that uranium is the major component of HLRW, it is required to go in depth in the analysis of the chemistry of the reaction of this element within bentonites. The determination of uranium under the conditions of HLRW, including the analysis of silicate matrices before and after the uranium-bentonite reaction, was investigated. The performances of a state-of-the-art and widespread radiochemical method based on chromatographic UTEVA resins, and a well-known and traditional method based on solvent extraction with tri-n-butyl phosphate (TBP), for the analysis of uranium and thorium isotopes in solid matrices with high concentrations of uranium were analysed in detail.In the development of this comparison, both radiochemical approaches have an overall excellent performance in order to analyse uranium concentration in HLRW samples. However, due to the high uranium concentration in the samples, the chromatographic resin is not able to avoid completely the uranium contamination in the thorium fraction.

A radiometric and petrographic interpretation of discrepancies on uranium content in samples collected at Alte Madonie Mounts region (Sicily, Italy)

The main goal of this work is to evaluate a correlation between anomalous Uranium (U) content and petrographic features of some soil and rock samples collected at Alte Madonie Mounts region (North-central Sicily, Italy). A total of 41 samples of selected soils and rocks were collected, powdered, dried and sealed in “Marinelli” beakers for 20 days before the measurement to ensure that radioactive equilibrium between 226Ra and 214Bi was reached. Gamma-ray spectrometric analysis was used to quantify radioactivity concentrations. Mineralogical and chemical features of the samples were determined by X-ray Fluorescence (XRF), X-ray Diffractometry (XRD), Attenuated Total Reflection-Fourier Transform Infrared (ATR-FTIR) and Scanning Electron Microscope – Energy Dispersive Spectrometry (SEM-EDS) analyses.The average values of concentrations of 226Ra, 228Ac and 40K were respectively 30, 17 and 227 Bq kg−1 while the greatest values were 134, 59 and 748 Bq kg−1. Linear relationships were observed between 226Ra, 228Ac and 40K concentrations: the activities of 226Ra and 228Ac were comparable, while those of 40K were about 10 times greater. An exception was highlighted for a group of samples where 226Ra activities were much higher than expectations. Chemical compositions and mineralogical features of the samples have made it possible to justify these anomalies.

Determination of Uranium Concentration in child teeth by track detector CR-39 in same middle and south regions of Iraq

The study of determing Uranium concentration in samples of teeth is the first of its kind in the Iraq . In this study Uranium concentration has been measured was (32) samples of child teeth distributed on the some of middle and south governorate of Iraq (Muthana – Dekar – Basrah – Najaf – Karbalah – Waset – Babel – Baghdad) . The Uranium concentration in teeth samples has been measured by using fission tracks registration in (CR-39) track detector that caused by the bombardment of (U235) with thermal neutrons falx from (24Am.Be) neutron source that has flux of (5x103n.cm-2S-1). The result obtained show that the Uranium concentrations in governorates were (0.18ppm), (0.172ppm), (0.160ppm), 0.150ppm) (0.89ppm), (0.07ppm) , (0.052ppm), (0.020ppm) (0.089ppm), (0.07ppm) , (0.052ppm) , (0.020ppm) (0.089ppm), (0.07ppm) , (0.052ppm) , (0.20ppm) respectively . As a conclusion from the study of Uranium concentration in Muthana governorate that found to be higher than Dekar and Basrah , Najaf , Karbalah, Waset , Babel and Baghdad . These result are higher thin the Uranium concentrations in one studies in Barazil – Bahia state its (0.016ppm) , and in another study in British about (0.018-0.079ppm).

Determination of Uranium Concentration in child teeth by track detector CR-39 in same middle and south regions of Iraq

The study of determing Uranium concentration in samples of teeth is the first of its kind in the Iraq . In this study Uranium concentration has been measured was (32) samples of child teeth distributed on the some of middle and south governorate of Iraq (Muthana – Dekar – Basrah – Najaf – Karbalah – Waset – Babel – Baghdad) . The Uranium concentration in teeth samples has been measured by using fission tracks registration in (CR-39) track detector that caused by the bombardment of (U235) with thermal neutrons falx from (24Am.Be) neutron source that has flux of (5x103n.cm-2S-1). The result obtained show that the Uranium concentrations in governorates were (0.18ppm), (0.172ppm), (0.160ppm), 0.150ppm) (0.89ppm), (0.07ppm) , (0.052ppm), (0.020ppm) (0.089ppm), (0.07ppm) , (0.052ppm) , (0.020ppm) (0.089ppm), (0.07ppm) , (0.052ppm) , (0.20ppm) respectively . As a conclusion from the study of Uranium concentration in Muthana governorate that found to be higher than Dekar and Basrah , Najaf , Karbalah, Waset , Babel and Baghdad . These result are higher thin the Uranium concentrations in one studies in Barazil – Bahia state its (0.016ppm) , and in another study in British about (0.018-0.079ppm).

Application of fission track technique for estimation of uranium concentration in drinking waters of Punjab

Drinking water samples were collected from four different districts, namely Bhatinda, Mansa, Faridkot and Firozpur, of Punjab for ascertaining the U(nat.) concentrations. All samples were preserved, processed and analyzed by laser fluorimetry (LF). To ensure accuracy of the data obtained by LF, few samples (10 nos) from each district were analyzed by alpha spectrometry as well as by fission track analysis (FTA) technique. For FTA technique few μl of water sample was transferred to polythene tube, lexan detector was immersed in it and the other end of the tube was also heat-sealed. Two samples and one uranium standard were irradiated in DHRUVA reactor. Irradiated detectors were chemically etched and tracks counted using an optical microscope. Uranium concentrations in samples ranged from 3.2 to 60.5 ppb and were comparable with those observed by LF.

DETERMINATION OF URANIUM CONCENTRATION IN TEETH MALE SAMPLES USING FISSION TRACKS IN CR-39 FROM DIFFERENT COUNTRIES.

The present study was under taken to measure the uranium concentration in female teeth samples collected from different nationalities. The determination of uranium concentration in these samples has been done by using CR-39 track detector. The nuclear reaction is used as a source of nuclear fission fragments is (n,f) obtained by the bombardment of U-235 with thermal neutrons with flux (5x10 3 n/cm 2 .s) was used from ( Am-Be) neutron source. The concentration values were calculated by a comparison with standard samples which prepared. The obtained results show that the concentration is ranging from (0.58 0.7ppm) in Oman and Uae to (0.35 0.03ppm) in Iraqi for male, the uranium concentration was the highest in Oman and Uae for female.

Analysis of uranium and isotopic ratio measurement in fish and marine invertebrates from the North Adriatic Sea by inductively coupled plasma mass spectrometry.

Uranium analysis in fish, echinoderms and shellfish samples collected in the north part of the Adriatic Sea is presented. The aim of the work was to evaluate uranium concentrations in samples of this kind, and also to investigate possible contamination from depleted uranium (DU) in consequence of the war operations previously conducted in that area. DU contamination was checked by measuring the (235)U/(238)U isotope ratio. The samples were dissolved according to the EPA 3052 procedure, and the determinations were performed by inductively coupled plasma mass spectrometry (ICP-MS), optimized in order to perform isotope ratio measurements with good precision. The method was validated by evaluating the recovery from spiked samples; results in the range 93-107% were obtained. The isotope ratio measurement was evaluated in terms of accuracy and precision by analyzing the certified reference materials IAEA 326 and GBW 07305, and good agreement with the certified values was obtained here also. The concentration of uranium was higher in invertebrate samples than in fish (0.3-2 microg/g of U vs. 0.05-0.1 microg/g, respectively). The isotope ratio measurements for all the samples gave values very similar to the natural ratio, permitting exclusion of the presence of DU.

Geochemical investigations for uranium in some areas of Himachal Pradesh using solid state nuclear track detectors

Fission track technique has been used to estimate uranium concentration in the samples of soil, rock and plants collected from some areas of Bilaspur, Mandi and Kulu districts of Himachal Pradesh, India. Uranium concentration in soil samples has been found to vary from 2.16 to 22.50 ppm., in rock samples from 1.41 to 10.34 ppm and in plants from 0.55 to 2.73 ppm. The anomalous uranium values have been obtained in soil, rock and plant samples from Thagan Nala region of Kulu district.

Radon exhalation rate and uranium estimation in rock samples from Bihar uranium and copper mines using the SSNTD technique

Widespread uranium mineralization is associated with copper, nickel and other sulphides in the Singhbhum shear zone developed at the northern margin of the Singhbhum craton in the state of Bihar of India. The south-eastern part of the shear zone between Surda-Mosabani-Badia is rich in copper mineralization while the central part between Jaduguda-Bhatin-Nimdih and Narwapahar-Garadih-Turamdih is enriched in uranium. In the present study, trace uranium concentration in geological samples from the Mosabani copper mine and the Narwapahar and Jaduguda uranium mine areas have been determined using fission track registration technique. For the measurement of the radon exhalation rate, the `can technique' using alpha sensitive LR-115 type II plastic track detectors were used. Uranium concentrations were found to vary from 1.5 to 2097.9 ppm whereas the radon exhalation rate varied from 0.2 to 19.2 Bq m −2 h −1. The values of radon exhalation rate from crushed rock and soil samples are found to correspond with the measured values of uranium in the corresponding samples. A positive correlation has been found between radon exhalation rate and uranium concentration in the samples. The linear coefficients are found to be 0.40, 0.98 and 0.95 in the Mosabani, Narwapahar and Jaduguda mine areas respectively. High values of radon exhalation in subsurface mines like Jaduguda (depth∼800 m) and Mosabani (depth>1000 m) seem to emphasize the need for adequate ventilation for the removal of radon and its progenies from the mines.

A sensitive method for the determination of uranium in biological samples utilizing kinetic phosphorescence analysis (KPA)

Kinetic phosphorescence analysis is a technique that provides rapid, precise and accurate determination of uranium concentration in aqueous solutions. This technique utilizes a laser source to excite an aqueous solution of uranium, and measures the emission luminescence intensity over time to determine the luminescence decay profile. The lifetime of the luminescence decay profile and the linearity of the log luminescence intensity versus time profile are indications of the specificity of the technique for uranium determination. The luminescence intensity at the onset of decay (the initial luminescence intensity), which is the luminescence intensity at time zero after termination of the laser pulse used for excitation, is proportional to the uranium concentration in the sample. Calibration standards of known uranium concentrations are used to construct the calibration curve between the initial luminescence intensity and uranium concentration. This calibration curve is used to determine the uranium concentration of unknown samples from their initial luminescence intensity. We developed the sample preparation method that allows the determination of uranium concentrations in urine, plasma, kidney, liver, bone spleen and soft tissue samples. Tissue samples are subjected to dry-ashing in a muffle furnace at 600°C and wet-ashing with concentrated nitric acid and hydrogen peroxide twice to destroy the organic component in the sample that may interfere with uranium determination by KPA. Samples are then solubilized in 0.82 M nitric acid prior to analysis by KPA. The assay calibration curves are linear and cover the range of uranium concentrations between 0.05 μg 1 −1 and 1000 μg 1 −1 (0.05–1000 ppb). The developed sample preparation procedures coupled with the KPA technique provide a specific, sensitive, precise and accurate method for the determination of uranium concentration in tissue samples. This method was used to quantify uranium in different tissue samples obtained over a period of 90 days following a single intraperitoneal uranium dose of 0.1 mg kg −1 in rats.

Determination of uranium concentration in domestic water samples by fission track method

The sensitive and simple fission track detection technique using a dry method with Melinex-0 plastic track detector has been applied for the determination of uranium concentration in samples of domestic water supply plants collected from different states of India, namely West Bengal, Uttar Pradesh, Rajasthan, Punjab and Delhi. Our analyses show that uranium concentration of water samples collected from different types of domestic water supply plants vary from 0.6±0.02 to 19.2±0.6 μg/l. The present investigations may be useful from the point of view of radiation hygiene.

Geochemical indicator of the efficiency of fractionation of the Skaergaard intrusion, East Greenland

SummaryWhen magmatic fractionation involves the settling and removal of crystals from the body of magma, the efficiency of the fraetionation process may be defined as the degree of separation of the solid from the liquid phase. An expression is given that relates efficiency to the amount of mesostasis, or crystallized trapped liquid, in an igneous cumulate. The uranium contents of samples from a 349-m-long drill-core of part of the lower and hidden zones of the Skaergaard intrusion are used as a quantitative indicator of the amounts of mesostasis in the cumulates. There are marked changes in the amount of mesostasis over the length of the core and the average efficiency of fractionation was 85 %.