Amount Of Uranium Research Articles

Uranium Uptake in Paracentrotus lividus Sea Urchin, Accumulation and Speciation.

Uranium speciation and bioaccumulation were investigated in the sea urchin Paracentrotus lividus. Through accumulation experiments in a well-controlled aquarium followed by ICP-OES analysis, the quantification of uranium in the different compartments of the sea urchin was performed. Uranium is mainly distributed in the test (skeletal components), as it is the major constituent of the sea urchin, but in terms of quantity of uranium per gram of compartment, the following rating: intestinal tract > gonads ≫ test, was obtained. Combining both extended X-ray Absorption Spectroscopy and time-resolved laser-induced fluorescence spectroscopic analysis, it was possible to identify two different forms of uranium in the sea urchin, one in the test, as a carbonato-calcium complex, and the second one in the gonads and intestinal tract, as a protein complex. Toposome is a major calcium-binding transferrin-like protein contained within the sea urchin. EXAFS data fitting of both contaminated organs in vivo and the uranium-toposome complex from protein purified out of the gonads revealed that it is suspected to complex uranium in gonads and intestinal tract. This hypothesis is also supported by the results from two imaging techniques, i.e., Transmission Electron Microscopy and Scanning Transmission X-ray Microscopy. This thorough investigation of uranium uptake in sea urchin is one of the few attempts to assess the speciation in a living marine organism in vivo.

Hyperbranched topological swollen-layer constructs of multi-active sites polyacrylonitrile (PAN) adsorbent for uranium(VI) extraction from seawater

With the depletion of terrestrial uranium deposits, a large amount of uranium(VI) (U(VI)) in seawater has attracted the attention of researchers and energy suppliers. However, the extremely low concentration of U(VI) and the complex environment enhance the difficulty of extracting U(VI) from seawater. In this study, a multi-active polyacrylonitrile (PAN) adsorbent was constructed to extract U(VI) from seawater. Poly(amido)amine (PAMAM) with hyperbranched topology was grown onto the surface of PAN fiber by a multi-step method, forming a swollen layer in water. The highest adsorption capacity of the material reached 555.5 mg/g. Importantly, during a continuous 50-day simulated seawater dynamic adsorption process, the material reached an adsorption equilibrium in 15 days, with the adsorption amount of 1.3 mg/g. The ocean test in the Yellow Sea of China showed that the adsorption capacity of the material was 0.6 mg/g in 34 days in seawater environment. The effect of molecular chain conformation and swelling behavior on adsorption properties were investigated. The study on the adsorption mechanism of the material shows that the lone pair of electrons of the N atom coordinates with U(VI).

Uranium supply potential from phosphate rocks for Argentina's nuclear power fleet

Argentina's nuclear reactor fleet provides about 10% of the country's electricity, and it is foreseen to increase nuclear power production in the future. Although most Argentinians accept nuclear power generation, public opinion is not in favor of uranium mining and all uranium needs are presently met by uranium imports at costs above international market prices (both spot and long-term contracts). Argentina also imports considerable amounts of phosphate rock and phosphate fertilizer to supply its agricultural industry. It is well-known that phosphate rocks and phosphate fertilizers can contain elevated amounts of associated uranium that is dissipated on agricultural soils if it is not recovered during fertilizer production. In this work, we estimate the amount of uranium that can be recovered from imported phosphate rock, determine the amount of uranium that could theoretically be recovered from all phosphate fertilizers used in Argentina and discuss potential uranium recovery from identified domestic phosphate rock resources.

Study on carbonation technology of alkaline uranium mother liquor

The characteristics of the main components of alkaline uranium mother liquor: A small amount of uranium, a certain amount of hydroxide, and a large amount of carbonate. Through the analysis of chemical reaction and diffusion about transfer between mother liquor and CO2, the influencing factors of mother liquor carbonation were determined: Gas-liquid transfer, reactant concentration, reaction temperature, etc. Tower counter-current was selected to investigate the influence of different types of fillers on carbonation effect. The stainless steel triangular spiral filler was optimized. The filling tower device for carbonation of uranium mother liquor was finalized, which greatly improved the gas-liquid distribution efficiency and carbon dioxide absorption rate. The effect of residual alkali concentration and reaction temperature of mother liquor on carbonation effect was investigated. The technology realizes the conversion of sodium hydroxide to sodium carbonate in the mother liquor. When sodium carbonate is converted to sodium bicarbonate, it can be converted to the saturated concentration of sodium bicarbonate, and CO2 is absorbed in both stages. The device can be used to control the degree of carbonation of the mother liquor according to the demand, and be returned as leaching agent or eluent, realized the full reuse of the remaining alkali in the mother liquor.

Mini Subcritical Nuclear Reactor

A mini subcritical nuclear reactor was designed using Monte Carlo methods. The reactor has light water as moderator, natural uranium as fuel, and a 239PuBe neutron source. In the design uranium fuel was modeled in an arrangement of concentric rings: 8.5, 14.5, 20.5 26.5, 32.5 cm-inner radius, 3 cm-thick, and 36 cm-high. Different models were made from a single ring of natural uranium to five rings. For each case, the neutron spectra, the neutron fluence distribution, the effective multiplication factor, the amplification factor, and the reactor power were estimated. The ambient dose equivalent rate outside the mini reactor was also estimated. The maximum value for the keff (0.78) was obtained when five rings of fuel were used; this value is close to 0.86 which belongs to a Nuclear Chicago subcritical reactor which requires almost twice the amount of uranium than the mini subcritical reactor.

Uranium resources in EU phosphate rock imports

Most European countries import phosphate rocks for mineral phosphate fertilizer production. In 2017, approximately 5.5 million t phosphate rocks were imported into the EU-28 and subsequently processed. Phosphate rock can contain relevant amounts of accompanying uranium as well as rare earth elements that can be recovered during phosphate fertilizer production. Recovering uranium from phosphate rock is a proven process that has been used on an industrial scale in North America, Europe, and Asia in the 1980s until decreasing uranium prices in the 1990s made this practice uneconomic. In this work, we estimate the amount of uranium contained in EU phosphate rock imports in 2017 using publicly available data from Eurostat as well as average uranium concentrations found in the exporting countries and discuss potential recoverable quantities. Results of this estimate indicate that a maximum of 334 t natural uranium could have theoretically been recovered from 2017 EU phosphate rock imports. This amount of uranium could have supported approximately 2.1% of the EU nuclear power fleets 2016 natural uranium requirements and is of the same order of magnitude as domestic EU uranium production.

Chemical relative dating of skeletons of the Iron Age cemetery of Tabriz on the basis of fluorine, uranium, and nitrogen content

Relative dating of archaeological bones by the measurement of fluorine, uranium, and/or nitrogen content is a well-established method, where the content of these elements in the bone structure must be determined. This research aims to study the human skeletal samples of Iron Age site of Blue Mosque in Tabriz, IRAN, on the basis of FUN relative dating method. In this way, the amount of fluorine in the selected samples was measured by UV–Vis spectrophotometry method, while the amount of uranium and nitrogen was determined by ICP-MS, and CHNS and Kjeldahl techniques, respectively. Totally, four bone samples of the skeleton from the cemetery were selected to be relatively dated. The results showed that sample no. 81.9 is the first one buried. Although the nitrogen content of this sample was the same as that of sample no. 80.6, but due to its higher concentration of fluorine and uranium compared to the other samples, it was likely the oldest sample studied at this work. While sample no. 80.6 had the lowest nitrogen content, but due to its lower levels of fluorine and uranium, it could be considered as the youngest,. Also, comparing the relative age of the two samples, no. 81.7 and no. 81.8, it can be concluded that sample no. 81.8 has spent more time under the soil. The results of this study clearly showed the necessity of applying all the three types of relative chemical dating methods (fluorine, uranium, and nitrogen dating) alongside, which is known as the FUN dating method.

Study of Earth’s Heat Flux by Means of Geoneutrino Detection

The heat flux from the Earth’s interior and its connection with the number of neutrinos recorded by detectors at the Earth’s surface are discussed. The values predicted for the geoneutrino fluxes may be matched with experimental data, but the observed flux of the Earth’s internal heat requires the presence of a larger amount of radioactive elements. The amount of uranium and thorium within the Earth is constrained by measurements performed with the aid of modern geoneutrino detectors. This makes it possible to explain completely a flux of 50 TW. There are indications that the flux from the Earth’s interior is 200 to 250 TW. Such a flux could be explained only by the presence of a substantially larger amount of potassium in the Earth. In order to determine precisely the heat flux from the Earth’s interior, it is necessary to measure completely the flux of antineutrinos from all heat-releasing isotopes, including the flux of neutrinos from 40K decay. Possibly, this flux has already been observed at the Borexino detector.

Tendencies and Prospects of the Ukrainian Nuclear Industrial Complex Development

The article analyzes development trends of the nuclear-industrial complex. Among the main problems of development of nuclear-industrial complex determined inadequate legal framework, lack of investment. The required amount of enriched uranium in nuclear fuel purchased by Ukraine only in the Russian Federation. Russia supplies the stockpile of uranium-235 after enrichment not less than 0.3%. The necessity of development sequence the stages of the innovation-oriented development of nuclear-industrial complex of Ukraine on the basis of strategic determinants. Directly the nuclear-industrial complex, which is the leading element of the nuclear energy complex of Ukraine can be considered a complex sector of the national economy that includes production of uranium, which forms the basis to meet the needs of nuclear power plants in natural uranium in the medium and long term; Zirconia production, which includes the establishment of the production of zirconium, which is the main structural material for the fabrication of nuclear fuel, given its unique physical properties of the weak interaction with neutron flux in the reactor core; manufacture of ion-exchange materials and to ensure the full production of uranium of Ukraine; production of fuel assemblies and components as a key link in the creation of our own nuclear-fuel cycle; research, design and information support of scientific research. In Ukraine there is no specialized institution that would deal with the coordination of the research questions regarding the development of nuclear-industrial complex. The contribution of the nuclear-industrial complex of Ukraine in the creation of gross domestic product is not significant, but its role is important in ensuring economic security and achieving energy independence. The basic principles for the development of nuclear-industrial complex should be reflected in the state Program of development of the industry and development strategy of the region. For the development of nuclear-industrial complex, it is advisable to use an innovative approach. This approach is represented as a set of three interconnected units, namely: methodical-information unit; diagnostic-estimated; estimating procedure. Reasonably necessary to increase the volume of uranium production, increase the level of its enrichment and at the same time to solve environmental issues on waste management.

Moderate-Breeding Fast Reactors and the Structure of Nuclear Power

The replacement of thermal reactors by fast reactors which are now being designed is analyzed. It is proposed that the nuclear power system will develop on the basis of thermal reactors approximately up to the middle of the 21st century, after which fast reactors with breeding ratio somewhat greater than 1 will start to replace them. The demand for the amount of native uranium in implementing such a strategy and the duration of the transitional period to a closed fuel cycle based on fast reactors are evaluated. It is shown that by the end of the 22nd century it will be possible to completely replace thermal reactors and do away with using native uranium in them.

Development of clearance verification equipment for uranium-bearing waste

Dismantled materials generated from nuclear facilities are reused or directed to repository sites. If scrap metals with complicated shapes can be cleared, the amounts of radioactive waste can be reduced. A clearance verification system is constructed to determine the amount of uranium in decontaminated metals in a drum using the 1.001 MeV gamma rays of 234mPa, produced in the decay of 238U. The experimental study with simulated waste drums demonstrated that the quantification errors of uranium fall within 25% for 0.5 g of uranium.

The preparation and properties of the UC1-xNx solid solutions by pulses laser carbonitriding

The UC1-xNx solid solution modified layers that improve corrosion resistance and surface hardness of uranium were prepared by pulsed laser irradiating the surface uranium in the mixed atmospheres where the partial pressure ratios of CH4 to N2 are 1:2, 1:1 and 2:1, respectively. The SEM images show that the distribution of micro-cracks in the modified layers decreases significantly with the increase of partial pressure of CH4 in the mixed atmospheres. The phase structure and chemical composition of the modified layers were investigated by XRD and AES. XRD results show that the composition of the carbonitride modified layers is mainly UC1-xNx solid solution, only with a small amount of free uranium and uranium dioxide. AES results reveal that the C and N contents in the UC1-xNx solid solution can be adjusted by the respective partial pressure of CH4 and N2. The U 4f, N 1s and C 1s core-level also confirmed that the UC1-xNx solid solution is the main component in the laser modified layers. Electrochemical polarization tests were conducted in 0.02 mol/L NaCl solution and the results indicated that the carbonitride modified layer prepared in an atmosphere where the ratio of CH4 to N2 at 1:2 have excellent corrosion resistance, its self-corrosive potential and self-corrosive current are −2.28 × 10−1 V and 5.56 × 10−8 A/cm2, respectively, while the values of the uranium are −5.67 × 10−1 V and 8.08 × 10−7 A/cm2, respectively. Nano-indentation measurement results show that the average hardness at different depths of these modified layers is between 7 GPa and 9 GPa, while the average value of the uranium is 4.1 GPa.

Analytical Method of Atomic Density Determination of Uranyl Nitrate Solution

A basic theory of an analytical calculation method to determine the atomic density of each individual nuclide contained in a homogeneous system of uranyl nitrate solution is presented. Atomic density or number density is a number of atoms or nuclides per cm3 or in a unit of atoms per barn-cm. This parameter is one of the important factors in defining the accuracy of neutronic calculations as such used in reactor core design. This work was carried out as part of neutronic design calculation of the SAMOP (subcritical assembly for 99Mo isotope production) project, where uranyl nitrate solution was used as fuel with uranium enrichment of 20%. A homogeneous solution made by dissolving uranyl nitrate salt [UO2 (NO3)2] into H2O solvent has been used as an approach to this model. Two kinds of solution were described i.e. one that was made based on the amount of UO2(NO3)2 dissolved in the solution and another one based on the amount of uranium in the solution. Expectedly this method can be used as an alternative way in estimating the atom density, solution density (g/cc) and the corresponding atom and weight fractions which is important in criticality calculations.

Novel Ion-Imprinted Carbon Material Induced by Hyperaccumulation Pathway for the Selective Capture of Uranium.

The development of nuclear energy is significant for resource sustainability. Uranium is the main nuclear fuel, and its effective absorption has captured the attention of researchers. In this study, the green technologies hyperaccumulation effect of the plant and ion-imprinted technology were used to prepare the uranium ion-imprinted hierarchically porous carbon material (II-HPC). At the same time, a nonimprinted hierarchically porous carbon (HPC) was prepared for comparison. The adsorption isotherm was fitted to the Langmuir model and maximum sorption capacity of II-HPC was 503.64 mg g-1 at 298 K. The kinetic data followed the pseudo-second-order model, indicating a dominant role of chemisorption. Initial studies were performed on a lab-scale simulated continuous-flow system for the adsorption kinetics testing of II-HPC in simulated seawater. The results showed that the amount of uranium adsorbed after 35 days was 0.379 mg g-1, which determined that II-HPC adsorbent is a potential material for enrichment of U(VI) from the seawater.

Study of radon reduction in gases for rare event search experiments

The noble elements, argon and xenon, are frequently employed as the target and event detector for weakly interacting particles such as neutrinos and Dark Matter. For such rare processes, background radiation must be carefully minimized. Radon provides one of the most significant contaminants since it is an inevitable product of trace amounts of natural uranium. To design a purification system for reducing such contamination, the adsorption characteristics of radon in nitrogen, argon, and xenon carrier gases on various types of charcoals with different adsorbing properties and intrinsic radioactive purities have been studied in the temperature range of 190–295 K at flow rates of 0.5 and 2 standard liters per minute. Essential performance parameters for the various charcoals include the average breakthrough times (τ), dynamic adsorption coefficients (ka) and the number of theoretical stages (n). It is shown that the ka-values for radon in nitrogen, argon, and xenon increase as the temperature of the charcoal traps decreases, and that they are significantly larger in nitrogen and argon than in xenon gas due to adsorption saturation effects. It is found that, unlike in xenon, the dynamic adsorption coefficients for radon in nitrogen and argon strictly obey the Arrhenius law. The experimental results strongly indicate that nitric acid etched Saratech is the best candidate among all used charcoal brands. It allows reducing total radon concentration in the LZ liquid Xe detector to meet the ultimate goal in the search for Dark Matter.

Activity concentrations of 238U and 226Ra in two European black shales and their experimentally-derived leachates

The production of gas from unconventional resources became an important position in the world energy economics. In 2012, the European Commission's Joint Research Centre estimate 16 trillion cubic meters (Tcm) of technically recoverable shale gas in Europe. Taking into account that the exploitation of unconventional gas can be accompanied by serious health risks due to the release of toxic chemical components and natural occurring radionuclides into the return flow water and their near-surface accumulation in secondary precipitates, we investigated the release of U, Th and Ra from black shales by interaction with drilling fluids containing additives that are commonly employed for shale gas exploitation.We performed leaching tests at elevated temperatures and pressures with an Alum black shale from Bornholm, Denmark and a Posidonia black shale from Lower Saxony, Germany. The Alum shale is a carbonate free black shale with pyrite and barite, containing 74.4 μg/g U. The Posidonia shales is a calcareous shale with pyrite but without detectable amounts of barite containing 3.6 μg/g U.Pyrite oxidized during the tests forming sulfuric acid which lowered the pH on values between 2 and 3 of the extraction fluid from the Alum shale favoring a release of U from the Alum shale to the fluid during the short-term and in the beginning of the long-term experiments. The activity concentration of 238U is as high as 23.9 mBq/ml in the fluid for those experiments. The release of U and Th into the fluid is almost independent of pressure. The amount of uranium in the European shales is similar to that of the Marcellus Shale in the United States but the daughter product of 238U, the 226Ra activity concentrations in the experimentally derived leachates from the European shales are quite low in comparison to that found in industrially derived flowback fluids from the Marcellus shale. This difference could mainly be due to missing Cl in the reaction fluid used in our experiments and a lower fluid to solid ratio in the industrial plays than in the experiments due to subsequent fracking and minute cracks from which Ra can easily be released.

Geochemistry and environmental impact of neutral drainage from an uraniferous coal waste heap

Mining in the former Novátor coal and uranium mine ceased in 1957 and a part of the wastes underwent spontaneous ignition in 1959–1970. Since the 1970s, the waste heap has been exposed to continuous weathering. The objective of this study was to assess to what extent the burnt and unburnt parts of the heap contribute to contamination of the local drainage system over a period lasting >40 years after the end of the mining. Analyses of water collected by lysimeters located on the slope of the heap have shown that the burnt part of the pile is still a source of aqueous sulfate and volatile elements (F, Se, and Pb) that have accumulated in this part of the heap during the self-ignition processes. The unburned part of the heap is mainly the source of aqueous carbonate, Mo, and U. The pH values of water flowing through the heap are in the narrow interval of 6.9–8.6. Rare layers of unburnt coal-bearing sediments rich in sulfides, where the pH values are between 2.9 and 3.7 are rather exceptional. These layers are the main source of Zn, Cu, and Co as a result of weathering of pyrite, chalcopyrite and sphalerite. The chemical composition of water draining from the heap ranges between the values determined in both its burnt and unburnt parts. The water collected at the foot of the heap in periods of low drainage contains high levels of aqueous sulfate (up to 400 mg/L), carbonate (up to 208 mg/L), U (up to 585 μg/L), Se (up to 50 μg/L), and Mo (up to 28 μg/L). On the other hand, the concentrations of these elements are lower in periods of high drainage. The pH values in the water drainage are in the near-neutral range, and uranium is mostly present as U(VI) with dominant phosphate and carbonate complexes in the order UO2(HPO4)22− > UO2(CO3)22− > UO2(CO3)34− > UO2CO30. The concentrations of sulfate and trace elements rapidly decrease with increasing distance from the heap as a result of dilution due to influx of water from uncontaminated streams. Stream sediments sampled in the marshy area at the foot of the heap contain high U contents (up to 460 mg/kg), and other elements (Cu, Pb, Zn, Cd, and Se) due to their sorption on Fe- and Mn-hydroxides, organic matter, and co-precipitation with carbonate or sulfate. Similarly, the amount of uranium and other trace elements in sediments decreases with the distance from the heap because of the influx of clastic material from uncontaminated streams. Consequently, potentially harmful elements in water and sediments represent environmental risks only in the close vicinity of the heap.

Genesis and Metallogenic Process of the Lujing Uranium Deposit, Southwest Jiangxi Province, China: Constraints of Micropetrography and S–C–O Isotopes

AbstractThe Lujing uranium deposit, located in the southeastern part of the Nanling metallogenic province, is one of the representative granite‐related hydrothermal uranium deposits in South China. Basic geology, geochemistry, and geochronology of the deposit have been extensively studied. However, there is still a chronic lack of systematic research on the genesis and metallogenic process of the deposit. Thus, we recently carried out an electron microprobe and stable isotopic analysis. The main research results and progresses are as follows:Uranium minerals in this deposit include coffinite, pitchblende, and uranothorite, and small amounts of uranium exist in accessory minerals in the form of isomorphism. Coffinite, which occurs predominantly as the pseudomorphs after pitchblende, also occurs as a primary mineral and is locally formed from the remobilization of uranium from adjacent uranium‐bearing minerals. The mineralizing fluid was originally composed of a magmatic fluid generated by late Yanshanian magmatism. The high As content of pyrite in ores may reflect the addition of meteoric water, or the formation water (or both), to the magmatic hydrothermal system. The δ34S values vary from −14.4‰ to 13.9‰ (mean δ34S = −3.9‰), showing a range that is similar to nearby Cambrian metamorphic strata and Indosinian granites, indicating that these host rocks represent the source of sulfur; however, the possibility of a mantle source cannot be completely ruled out. According to our new isotopic data and recent Pb isotopic data, we conclude that the uranium in ores was derived by leaching dominantly from the uranium‐rich host rocks, especially the Cambrian metamorphic strata. The δ13CPDB values (−8.75‰ to 1.40‰; mean δ13CPDB = −5.41‰) and δ18OSMOW values (5.45–18.62‰; mean δ18O = 13.02‰) of reddish calcite from the ore‐forming stage suggest that the CO2 in the mineralizing fluids was derived predominantly from the mantle, with a small component contributed by marine carbonates. Based on these new data and previous research results, this paper proposes that uranium metallogenesis in the Lujing deposit is closely associated with mafic magmatism resulting from crustal extension during the Cretaceous to Paleogene in South China.

ON THE POSSIBILITY OF THE RAPID ASSISTANCE TO PEOPLE AFTER A SINGLE EXPOSURE TO URANIUM HEXAFLUORIDE

Introduction. The accidental release of uranium hexafluoride (UHF) is associated with the pollution of the air of the working premises with its hydrolysis products, containing toxic substances (uranium and fluorine). The intake of UHF hydrolysis products by is related to a negative impact on the human body. The magnitude and the rate of the exposure are determined by the amount of deposited toxic substances. Known methods for the determination of these amounts are based on the study of involved biological media (urine, blood, postmortem examination of all organs), requiring time-consuming, sometimes are critical for the preservation of the human life. In this paper, we propose a theoretical method for the detecting the amount of the deposited toxic substances. The calculation is based on models constructed by authors of this article. They describe successively: pollution of the working premises with UHF hydrolysis products, the input of toxic substances in the human body, uranium and passing fluorine through the body. The first model includes the following processes: hydrolysis, the formation of aerosol particles as on the deposition gas molecules and the wall of working space as on the human skin, deposition of the aerosol particles on the floor of the working space. With continuity equations written for the concentrations of molecules of substances of interest to us, the analytical expressions for n(z,t) - the concentration of atoms of a toxic substance at the height z at the time t; j(t) - flux density of toxic substance atoms on the surface of the skin at the time t. The second and third models describe percutaneous intake and inhalation of uranium and fluorine consisting of UHF hydrolysis products entering the human body, as well as toxic substances passed through the body. Results. There are presented results of calculating the amounts deposited in the body of uranium fluoride at various time points. There is given a comparison of these values with the experimental data in the literature on the quantity of uranium and fluorine, which enters the body to cause various organic and functional changes. Conclusion. The theoretical method of determining a person’s level of the destruction was concluded to allow extending the prediction of the development of adverse effects of uranium and fluorine without its prior survey, and choose the most effective methods of healthcare provision.

Magnetic glutamine‐grafted polymer for the sorption of U(VI), Nd(III) and Dy(III)

AbstractBACKGROUNDThe nuclear power industry and other high‐tech industries require increasing quantities of uranium and rare‐earth elements (REEs). There is a need for materials that can competitively recover these metals from ore leachates (such as produced in the leaching of Egyptian ores).RESULTSA sorbent based on the chemical grafting of glutamine moieties on a magnetic polyacrylonitrile support was synthesized: polyacrylonitrile, crosslinked with 10% divinyl benzene in the presence of magnetite, was chemically modified by a series of grafting steps to produce a magnetic polyglutamine sorbent (MGLU). The sorbent was characterized by titration, elemental analysis, X‐ray diffraction (XRD), thermogravimetric analysis, Fourier‐transform infra‐red (FTIR) spectrometry and scanning electron microscopy (SEM). The sorption properties were tested as a function of pH; the sorption isotherms were modeled using the Langmuir equation (maximum sorption capacities: 2 mmol U g‐1 and up to 3.5 mmol g‐1 for Nd(III) and Dy(III)). The equilibrium is achieved within 1 h of contact. Metal desorption and sorbent recycling are highly efficient using acidic solutions; sorption/desorption performance remains stable for a minimum of 5 cycles. MGLU was tested for metal binding in multi‐metal solutions at different pH values.CONCLUSIONThis sorbent could be used for the recovery of REEs and uranium from simulated ore leachates. © 2017 Society of Chemical Industry