Comparison of different methods for uranium determination in water

Increasing the recovery and selectivity of 238U, 235U, and 234U extraction with tri-n-butyl phosphate in mine tailing samples with a high copper content

Abandoned Cu mine tailings may be associated high concentrations of U. However, the presence of stable cations such as Cu, Fe, Al, Ca, or Mg, etc. in high concentrations can reduce the chemical efficiency of the liquid-liquid extraction method with tri-n-butyl phosphate (TBP); it can also inhibit the electrodeposition of U on the stainless steel planchet where the sample is measured. In this work we studied an initial stage of complexation with ethylenediaminetetraacetic acid (EDTA) and a back extraction with different solutions: H₂O, Na₂CO₃, and (NH₄)₂CO₃ at room temperature and at 80 °C. The sensitivity of the method was 4.9·10^-4 Bq for ²³⁸U and ²³⁴U, and 2.3·10^-5 Bq for ²³⁵U. The validation of the method achieved 95% of the results when using a |ζ-score| ≤ ± 2.0 and a relative bias (RB[%]) ≤ ± 20% as the acceptance criteria. The recoveries obtained with the proposed method were higher than those achieved with the extraction method without initial complexation and re-extraction with H₂O for water samples. Finally, this method was applied in practice to study the tailing of an abandoned Cu mine and the activity concentrations of ²³⁸U and ²³⁵U were compared with those obtained by gamma spectrometry for ²³⁴Th and ²³⁵U. The means and variances of both methods showed no significant differences between these two isotopes.

A novel fluorescence sensor for uranyl ion detection based on a dansyl-modified peptide

It is of great significance to sensitively and selectively detect uranyl ion (UO₂²⁺) in environmental and biological samples due to the high risks of UO₂²⁺ to human health. However, such suitable sensors are still scarce. A novel fluorescence sensor based on a dansyl-modified peptide, Dansyl-Glu-Glu-Pro-Glu-Trp-COOH (D-P5), was efficiently synthesized by Fmoc solid phase peptide synthesis. As the first linear peptide-based fluorescence sensor for UO₂²⁺, D-P5 exhibited high selectivity and sensitivity to UO₂²⁺ over 27 metal ions (UO₂²⁺, Cr³⁺, Cu²⁺, Ba²⁺, Hg²⁺, Pb²⁺, Co²⁺, Ag⁺, Fe³⁺, Ca²⁺, K⁺, Mg²⁺, Mn²⁺, Na⁺, Ni²⁺, Cd²⁺, Zn²⁺, Al³⁺, Dy³⁺, Er³⁺, Gd²⁺, Ho³⁺, La³⁺, Lu³⁺, Pr³⁺, Sm³⁺, Tm³⁺) by a turn-off fluorescence response in 10 mM HEPES buffer (pH 6.3). The effects of anions such as S^2-, NO₃^-, SO₄^2- CO₃^2-, HCOO^-, antioxidant ascorbic acid and 4-nitrophenyl acetate on the selectivity for UO₂²⁺ detection were also studies. D-P5 sensor could be used for detecting UO₂²⁺ in a good linear relationship with concentration in the range of 0-8.0 μM with a low limit of detection of 83.2 nM. Furthermore, the interaction of the sensor with UO₂²⁺ was characterized by ESI-MS, IR, XPS and ITC measurements. The 1:1 binding stoichiometry between the sensor and UO₂²⁺ was measured by the job's plot and further verified by ESI-MS. The binding constant of the sensor with UO₂²⁺ was calculated to be 9.8 × 10⁴ M^-1 by modified Benesi-Hildebrand equation. ITC results showed that theΔH^θ andΔS^θ for the interaction of D-P5 with UO₂²⁺ were -(7.167 ± 1.25) kJ·mol^-1 and 66.5 J·mol^-1·K^-1, respectively. Time-resolved fluorescence spectroscopy indicated that the mechanism of fluorescence quenching of D-P5 by UO₂²⁺ ion was static quenching process. In addition, this sensor displayed a good practicality for UO₂²⁺ detection in lake water sample without tedious sample pretreatment.

A Novel Eco-Friendly and Highly Sensitive Solid Lead-Tin Microelectrode for Trace U(VI) Determination in Natural Water Samples

For the first time a solid state lead-tin microelectrode (diameter ϕ 25 µm) was utilized for U(VI) ion determination by adsorptive stripping voltammetry. The described sensor is characterized by high durability, reusability and eco-friendly features, as the need for using lead and tin ions for metal film preplating has been eliminated, and consequently, the amount of toxic waste has been limited. The advantages of the developed procedure resulted also from the utilization of a microelectrode as a working electrode, because a restricted amount of metals is needed for its construction. Moreover, field analysis is possible to perform thanks to the fact that measurements can be carried out from unmixed solutions. The analytical procedure was optimized. The proposed procedure is characterized by two orders of magnitude linear dynamic range of U(VI) determination from 1 × 10^-9 to 1 × 10^-7 mol L^-1 (120 s of accumulation). The detection limit was calculated to be 3.9 × 10^-10 mol L^-1 (accumulation time of 120 s). RSD% calculated from seven subsequent U(VI) determinations at a concentration of 2 × 10^-8 mol L^-1 was 3.5%. The correctness of the analytical procedure was confirmed by analyzing a natural certified reference material.

Modified Mesoporous Carbon Material (Pb-N-CMK-3) Obtained by a Hard-Templating Route, Dicyandiamide Impregnation and Electrochemical Lead Particles Deposition as an Electrode Material for the U(VI) Ultratrace Determination

In this paper, a dicyandiamide-impregnated mesoporous carbon (N-CMK-3), electrochemically modified in situ with lead film (Pb-N-CMK-3), was tested as an electrode material for U(VI) ultratrace determination. The prepared carbon material was characterized by XRD, SEM-EDX, Raman, FT-IR, XPS analysis and nitrogen sorption measurements. The changes of electrochemical properties of glassy carbon electrodes (GCE) after the N-CMK-3 and Pb-N-CMK-3 modification were studied using CV and EIS methods. The modification of the GCE surface by the N-CMK-3 material and Pb film increases the electroactive area of the electrode and decreases the charge transfer residence and is likely responsible for the electrochemical improvement of the U(VI) analytical signal. Using square-wave adsorptive stripping voltammetry (SWAdSV), two linear calibration ranges extending from 0.05 to 1.0 nM and from 1.0 to 10.0 nM were observed, coupled with the detection and quantification limits of 0.014 and 0.047 nM, respectively. The Pb-N-CMK-3/GCE was successfully applied for U(VI) determination in reference materials (estuarine water SLEW-3 and trace elements in natural water SRM 1640a).

Methods for radioactivity measurements in drinking water using gamma spectrometry

In this study, three methods to measure activity concentrations of radionuclides through high resolution gamma spectrometry are developed, optimized, and tested on drinking water samples. Two pre-concentration methods (partial evaporation and ion-exchange resins) were optimized for accuracy, precision, detection limits, costs, preparation, and measurements times. A new sampling method for ²²²Rn was designed and optimized to directly sample water from the tap, reducing and minimizing losses of radon during the sampling. A total number of 85 water samples were collected between 2017 and 2019 in collaboration with two drinking water suppliers in a wide area (~2000 km²) of the Veneto region, northeast Italy. These are the first results of radionuclides activity concentration in drinking water concerning a large extension in the foothill Veneto region. Finally, this study provides a first attempt of determining the spatial distribution and seasonal variations of radon activity concentration in drinking water in the study area.

Removal and recovery of U(VI) from aqueous effluents by flax fiber: Adsorption, desorption and batch adsorber proposal

•

Removal and recovery of uranium were investigated in a batch process.

•

Adsorbent characteristics were scientifically analyzed.

•

The maximum obtained U(VI) removal was ≈94.50% at pH of 4 and adsorbent dose of 1.2 g.

•

Adsorption data were analyzed using kinetic, isotherm and thermodynamic models.

•

Full scale batch adsorber unit was recommended.

Flax fiber (Linen fiber), a valuable and inexpensive material was used as sorbent material in the uptake of uranium ion for the safe disposal of liquid effluent. Flax fibers were characterized using BET, XRD, TGA, DTA and FTIR analyses, and the results confirmed the ability of flax fiber to adsorb uranium. The removal efficiency reached 94.50% at pH 4, 1.2 g adsorbent dose and 100 min in batch technique. Adsorption results were fitted well to the Langmuir isotherm. The recovery of U (VI) to form yellow cake was investigated by precipitation using NH₄OH (33%). The results show that flax fibers are an acceptable sorbent for the removal and recovery of U (VI) from liquid effluents of low and high initial concentrations. The design of a full scale batch unit was also proposed and the necessary data was suggested.

Uranium content in groundwater by laser fluorimetry; method validation and dose assessment

In this study, the total uranium concentration was determined in groundwater samples used for irrigation and/or drinking purposes and collected from private wells in Al Sharqiya region, Saudi Arabia. The uranium concentrations were measured by laser fluorimetry preceded by radiochemical treatment to eliminate the quenching effect due to the high total dissolved solids content in the groundwater samples. For method validation, some of the measured samples were analyzed for uranium isotopic activities and measured by alpha spectrometry. The results of the uranium concentrations obtained by laser fluorimetry and alpha spectrometry were in good agreement. The uranium concentrations in all the samples were below the World Health Organization (WHO) recommended limit of 30 μg L^-1. Two different approaches were followed to assess the annual effective dose from the ingestion of uranium in the analyzed groundwater samples. The annual effective doses determined by the two approaches were found to be in agreement, and varied from 2.9 to 10.2 μSv y^-1, with a mean value of 6.1 μSv y^-1, which is far below the WHO recommended level of 100 μSv/y. The modified laser fluorimetric procedure was found to be a good tool compared with other techniques for direct measurement of uranium concentrations in high total dissolved solids groundwater samples at low levels.

Determination of specific alpha-emitting radionuclides (uranium, plutonium, thorium and polonium) in water using [Ba+Fe]-coprecipitation method

The indicative dose (ID) is one of the parameters established in the current European directive for water intended for human consumption. To determine the ID, it is necessary to know the activity concentration of: ²³⁸U, ²³⁴U, ²²⁶Ra, ²¹⁰Po, ^239,240Pu and ²⁴¹Am. The existing methods to determine these radionuclides involve complex radiochemical separations (ionic exchange columns, extraction chromatography, etc.), followed by measurements with a semiconductor detector, laboratory procedures that are time-consuming and costly. As a lower cost alternative that reduces measuring and preparation times, avoids the need for a self-absorption correction and the use of tracers, and above all that can be used in any laboratory, methods based on liquid-liquid extraction and selective co-precipitation were developed. These methodologies offer high separation recovery and selectivity, and the measurements are made using a gas proportional counter or a solid ZnS(Ag) scintillation counter. The separation factor ranged between 91.4% and 100.0% for all alpha-emitting radionuclides across the different methods. The activity concentration for each method was computed through linear equations that represent the relationship between the activity and selectivity of the different alpha-emitting radionuclides. This mathematical procedure simplifies the radiochemical separations and provides more accurate activity concentrations. The results of the internal and external validation studies proved that the proposed method is suitable for determining ²⁴¹Am, ²²⁶Ra, uranium, plutonium, thorium and ²¹⁰Po in water samples.

Radioanalytical techniques for the determination of 238U, 226Ra and 210Pb in the environment

Different radiometric techniques for the determination of 238U, 226Ra and 210Pb are presented and compared in terms of detection limits with mass spectrometric techniques. It can be concluded that when samples with low activity concentrations have to be measured, the method of choice in the case of 238U should be either RNAA/INAA or alpha particle spectrometry. In the case of 226Ra and 210Pb the best performance can be expected by the alpha spectrometry, whereas drawback of waiting for establishing secular radioactive equilibrium of 210Pb with 210Po makes techniques like beta counting and LSC more attractive for the determination of 210Pb. In addition, a case study on monitoring the former uranium mine Žirovski vrh is presented along with the used methodology and the summarised measurement results.

Membrane optode for uranium(VI) ions preconcentration and quantification based on a synergistic combination of 4-(2-thiazolylazo)-resorcinol with 8-hydroxyquinaldine

A membrane optode was developed utilizing the 8-hydroxyquinaldine (HQ) facilitated preconcentration of UO(2)(2+) ions and subsequent colored complex formation of UO(2)(2+) with 4-(2-thiazolylazo)-resorcinol (TAR) in optode matrix. The composition of the membrane optode was optimized by scanning several extractants immobilized in different plasticized polymer matrices. It was observed that the chelating agent HQ along with an indicator TAR immobilized in the tri-(2-ethylhexyl)phosphate (TEHP) plasticized cellulose triacetate matrix (CTA) was best suited as an optode for the UO(2)(2+) ions in aqueous samples. On sorption of UO(2)(2+) in the optode matrix, TAR changes color of the optode from yellow to magenta having a maximum absorbance (lambda(max)) at 546 nm. The uptake of UO(2)(2+) ions in the optode was found to be pH dependent and was maximum (>90%) at pH above 3. The acetate buffer (0.1 mol L(-1) sodium acetate + 0.1 mol L(-1) acetic acid) was found to be necessary for the stable response. The optimum equilibration time for the optode (2 cm x 1 cm) was found to be 30 min in 10 mL aqueous sample containing acetate buffer (pH 4.75). The equilibration time was found to increase with increase in aqueous sample volume. The optode response was found to be linear in the UO(2)(2+) ions concentration range of 0.01-0.11 micromol L(-1) in tap water as well as aqueous solutions containing 0.1 mol L(-1) NaCl or NaNO(3). The tolerance to the presence of several cations and anions in the determination of UO(2)(2+) ion was studied. It was observed that the optode in the presence of buffer can tolerate presence of large amounts of interfering cations (Ce(4+), V(4+), Eu(3+), Al(3+), Fe(3+), Ni(2+), Cd(2+), Co(2+), Pb(2+), Hg(2+), Cu(2+) and Th(4+) ions) without hindering the sorption of UO(2)(2+) ions in the optode matrix. The present work indicated that 50 ppb UO(2)(2+) ions in 100 mL sample can easily be quantified using this optode. The optode was found to be fully reversible, can readily be regenerated by equilibrating it with 0.1 mol L(-1) HNO(3) and reusable up to three cycles. The applicability of the developed optode in real samples was studied by determining uranium in the ground water samples spiked with a known quantity of UO(2)(2+) ions.

Distribution of uranium in drinking water and associated age-dependent radiation dose in India

Exposure due to natural radiation is of particular importance because it accounts for the largest contribution (nearly 85 %) to the total collective dose of the world population. An attempt has been made to present the feasibility of uranium occurrence in drinking water samples from different states of India, by laser-induced fluorimetry. The associated age-dependent radiation dose was estimated by taking the prescribed water intake values of different age groups. The concentration of uranium obtained, i.e. 0.1 +/- 0.01 to 19.6 +/- 1.8 microg l(-1), is well below the drinking water guideline value of 30 microg l(-1). The annual ingestion dose due to uranium in drinking water for various age groups is found to vary from 0.14 to 48 microSv y(-1).

An improved radiochemical separation of uranium and thorium in environmental samples involving peroxide fusion

A radiochemical procedure for the accurate determination of uranium and thorium using peroxide fusion followed by ion exchange and extraction chromatography is described. The method of extraction of the element from solid samples is the most important factor in the investigation. It is demonstrated, by measuring a number of reference materials, that fusion with Na(2)O(2) ensures a complete destruction of the mineral lattice and greatly improves the determination of the true activity of actinides.