Amount Of Uranium Research Articles

High capacity amidic succinic acid functionalized mesoporous silica for the adsorption of uranium

The nuclear reactors operating worldwide are currently using the uranium mined from the resources available on the earth's crust. A significant volume of aqueous waste containing a small quantity of uranium was generated during the processing of ores. There is a growing demand to remove this toxic uranium from these aqueous streams, owing to the limit of tolerable daily intake (15 μg L−1) for uranium imposed by the World Health Organization. This demand throws huge challenges to the separation chemists to engineer the solid phase adsorbents having high capacity, excellent selectivity and satisfactory throughputs for processing a vast quantity of aqueous waste containing traces of uranium. In this context, the task specific amidic succinic acid (SUC) functional groups tailored on mesoporous silica having wide porosity and large surface area have been prepared and characterized by BET surface area, pore and particle size distribution, thermogravimetry, SEM-EDX analysis, FT-IR and Raman spectroscopy. The adsorption behavior of uranium (VI) from the aqueous phase on the tailored adsorbent (MCM-SUC) was studied as a function of pH of the aqueous phase, duration of equilibration, uranium concentration in the aqueous phase, and the results were compared with the adsorbent containing the same functional group but grafted on silica gel (Si-SUC), which exhibited adsorption capacity of 61 mg g−1. The fast kinetics of adsorption and significantly high Langmuir adsorption capacity of uranium (807 mgg −1), as compared to the other mesoporous adsorbents reported in literature, achieved in MCM-SUC was due to controlled synthesis of SUC functionalized mesoporous silica that favoured high degree of SUC number density on the mesoporous material. The adsorbed uranium was recovered using 0.1 M nitric acid.

Uranium Bioleaching from Low Grade Ore

The goal of the present work was to perform bioleaching of uranium from low grade ore from Vostok deposit (Republic of Kazakhstan), which was previously subjected to long-term acid leaching. The ore initially contained from 0.15 to 0.20% of uranium in the form of uraninite, but ore samples used in the study contained about 0.05% of uranium, as it was exhausted during acid leaching, and uranium was partially leached. Representative samples of ore were processed in 1 m columns, leach solutions containing 5, 10, 20 g/L of sulfuric acid and bacterial cells (about 104) were percolated through the ore. Leaching was performed at ambient temperature for 70 days. In one of the percolators, the leaching was performed with leaching solution containing 10 g/L of H2SO4, cells of A. ferrooxidans, and 0.5 g/L of formaldehyde. Leaching with the solution containing 5, 10, and 20 g/L of sulfuric acid made it possible to extract 50, 53, and 58% of uranium. Addition of formaldehyde in leach solution led to the decrease in uranium extraction extent down to 37%. Thus, the results of the present work demonstrated that uranium ore exhausted during long-term acid leaching may be successfully subjected to bioleaching, that allows extracting residual quantities of uranium. Leaching rate of uranium from exhausted ore depended on both sulfuric acid concentration and microbial activity of bacteria isolated from acid mine drainage, formed on uranium deposit. In the same time, acid mine drainage may be used as a source of inoculate, to start bioleaching process.

Assessment of Uranium in Urine Samples of Primary School Students

The environmental monitoring of radon in the children urine has been carried out by using solid state nuclear track detector CR-39. This study has been undertaken for the purpose of health risk assessments. The concentration of uranium values excreted with the boy's urine samples ranged from 0.203 Bq.L-1 (1.246 ng/L) and 2.201 Bq.L-1 (13.486 ng/L) with an average value of 0.698 Bq.L-1 (4.007 ng/L). While the concentration of uranium values excreted with the girl's urine samples ranged between 0.290 Bq.L-1 (1.777 ng/L) and 0.675 Bq.L-1 (4.135 ng/L), with an average value of 0.474 Bq.L-1 (2.901 ng/L). The amount of uranium deposited in the kidneys, according to ICRP's biokinetic model, and the annual radiation dose were also calculated. All values of the study samples were within the normal range and do not indicate any health hazard.

Experimental and theoretical studies of spherical β-cyclodextrin modified titanium dioxide composites for uranium removal

With the fast development of the nuclear industry, it is inevitable that a considerable amount of uranium (U) is discharged into the environment during mining, use, and disposal processes, which can result in serious radioactive contamination. In this study, the spherical β-cyclodextrin modified titanium dioxide (β-CD/TiO2) was prepared by a simple hydrothermal method for the capture of U(VI). The removal of U(VI) on β-CD/TiO2 was dependent on solution pH. The maximum adsorption capacity of β-CD/TiO2 at pH 5.0 reached 129.8 mg/g for U(VI). The thermodynamic study confirmed that the capture of U(VI) was a spontaneous process. According to the XPS analysis, the hydroxyl groups of β-CD/TiO2 were responsible for U(VI) removal, which was further demonstrated by DFT calculation at the molecular level. The findings presented in this study are important to the removal of radionuclides from wastewater.

Determination of trace amounts of uranium in plutonium oxide by wavelength dispersive X-ray fluorescence spectrometry

This paper presents a wavelength dispersive X-ray fluorescence (WDXRF) spectrometry based non-destructive methodology for the determination of trace level uranium in PuO2 powder. The methodology requires pelletization of PuO2 powder standards and samples using a hydraulic press, measuring WDXRF spectra of calibration standards and samples using U Lα X-ray as analytical line and analyzing the samples for trace amounts of uranium. The reproducibility of the analytical results using this methodolgy was found to be better than ± 5% (RSD, n = 5) for uranium in the range of 200–1000 µg g−1. The samples were also analyzed for U by ICP-OES and WDXRF values showed a close agreement with those obtained by ICP-OES.

Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium

The 99Mo production in a 2 MW molten salt reactor using liquid low-enriched uranium (LEU) fuel has been evaluated. The batch-wise extraction period of 99Mo is optimized to be one day corresponding to 9415 6-day Ci/week of the 99Mo production rate. The required amount of uranium is only 4.77 kg annually. The required chemically reprocessed amount of FPs is about 58.4 g annually, accounting for only 4.9% of the solid LEU target method under the identical production capacity of 99Mo.

Gene expression response of mutagenic breeding of Acidithiobacillus sp. FJ2 to different concentrations of uranium low grade ore

Acidithiobacillus ferrooxidans ( At. f ) is a bacterium involved in the bioleaching process . In the present study, we investigated the effects of Acidithiobacillus sp. FJ2 induced with diethyl sulfate (DES) as mutagen on the bioleaching of low grade uranium ore. The comparison was carried out within 5, 10, 15, 25 and 50% uranium ore pulp densities in the bioleaching system. The impact of the induction of Acidithiobacillus sp. FJ2 was determined by Eh and pH values, concentrations of Fe 2+ and uranium extraction rates at 24 h intervals. The results showed that DES with 0.8% may lead to an obvious change on bacteria leading to improvement of bioleaching capability in 5, 10, 15% pulp densities. However, the bioleaching activity of the original bacteria was more efficient than DES-induced bacteria at 25 and 50% pulp densities. The gene expression results in 0.8% DES treated bacteria indicated that the bacteria attempt to adjust in the bioleaching systems (with different pulp densities) through decreased cyc2 and increased rus , cyc1 and coxB levels. These results suggest that uranium may induce oxidative stress in the wild and treated strains in the high pulp density, while the bacteria tried to survive and gain more energy from the iron oxidation. However, when the amount of uranium increased, the mutants couldn’t cope up woth the enhanced stress in 25 and 50% pulp densities. It may be due to inhibitory effect of uranium toxicity on adaptive processes which may change the trends.

New insight studies of the secondary phase formation under repository conditions

ABSTRACTIn a deep geological repository (DGR) scenario, uranium oxidized in aqueous systems will be stabilized as UO22+ (hexavalent uranium), as a consequence of tetravalent uranium oxidation by radiolytic byproducts. Uranyl cationic species (UO22+) in different speciation forms are expected to be found at the whole pH range conditions. The importance of UO22+ lies in its potential incorporation of trace radioelements onto secondary uranyl phases. In view of the difficulty of U chemistry in natural groundwater, it is necessary to improve speciation assessment techniques so as to understand chemical processes. Raman spectroscopy has been shown as a powerful tool to analyze the speciation of various actinyl (UO22+,NpO2+ and PuO22+) and to determine the distribution of those elements which are more likely to be stable in a near-field groundwater environment. Therefore, the aim of this work is to follow UO22+ changes as a consequence of γ radiation in aqueous media under DGR conditions, and to understand the behavior of UO22+ as a function of aqueous media, which help to understand and predict the potential precipitation of the solid phases formed. In this work, the use of Raman spectroscopy adapted to the empirical analysis of different nuclear applications for initial uranium concentrations 0.04M at ambient atmosphere is shown, i.e. as monitoring tool for UO22+ precipitation as a function of pH, studying UO2(NO3)2·6H2O stability in aqueous solutions representative of groundwater, in particular at ionic strength I = 0.02 – 0.4 M and pH from 7 to 13.2; and to evaluate the effect of γ radiation fields. At 10−4-10-3 M of radiolytically formed H2O2 concentration, the amount of uranium in solution decreased, as a results of secondary phases precipitation. The results obtained will be useful to the performance assessment studies of the Spent Nuclear Fuel (SNF) stored in DGRs. The work performed provides a partial picture of secondary phase formations, as a result of corrosion of SNF in a DGR.

Radionuclide distributions in Olympic Dam copper concentrates: The significance of minor hosts, incorporation mechanisms, and the role of mineral surfaces

Some iron oxide-copper-gold (IOCG) deposits contain variable amounts of uranium. Developing mineral deportment models for the radiogenic isotopes resulting from decay of 238U presents a singular technical challenge, as concentrations of 226Ra, 210Pb, and 210Po fall far below the detection limits achievable for most in situ analytical methodologies. The nanoscale secondary ion mass spectrometry (nanoSIMS) platform combines low detection limits with sub-micron resolution, revealing previously unseen spatial distribution patterns of radionuclides (RNs) in (and on) particles of copper sulphide concentrates. Many potential host minerals for these radionuclides can be readily predicted based on chemical behaviour, periodic table trends, and published studies documenting likely host minerals. Using nanoSIMS data for ores and metallurgical products from the Olympic Dam IOCG deposit and associated processing facilities, we present compelling evidence for the ability of certain minerals within the copper concentrates to host daughter radionuclides derived from uranium decay. Many of these minerals had not traditionally been considered or previously documented as such. These include high-abundance minerals hosting low concentrations of radionuclides, and several relatively low abundance minerals exhibiting remarkable radionuclide enrichment. Rutile, fluorapatite, fluorite, hematite, zircon, covellite, and molybdenite are all proven to be minor hosts of at least some members of the 238U decay chain, and are, collectively, important for establishing the overall RN budget. Surface effects are found to play a significant role, with elevated levels of 226Ra and 210Pb found on most available surfaces, irrespective of mineral, in acid-leached concentrate. Some rRNs, particularly 226Ra and 210Pb liberated from uranium minerals during sulphuric acid leaching, can become extensively redistributed throughout the concentrate, creating newly-formed RN hosts. This new mineralogical deportment information can be used in developing new flowsheets to enhance radionuclide removal without a corresponding loss of Cu. NanoSIMS has proven invaluable for elucidating the mineral-scale deportment of ultra-trace radionuclides throughout the processing circuit at Olympic Dam.

Magnetic assisted separation of uranium(VI) from aqueous phase using diethylenetriamine modified high capacity iron oxide adsorbent

Processing of uranium ore for the production of reactor-grade uranium results in the generation of large amount of aqueous waste containing small quantities of uranium, but higher than the guideline value (15 μg L−1) recommended by World Health Organization (WHO). The presence of uranium in aqueous waste poses several hazards and environmental issues due to the radioactive nature and migration behavior of uranium in the geosphere. In order to remove uranium (VI) from aqueous waste, the diethylenetriamine modified high capacity magnetic iron oxide adsorbent, abbreviated as Fe-DETA, was prepared and studied for the extraction of uranium from aqueous solutions. The Fe-DETA was characterized by X-ray diffraction, thermal analysis, infrared and Raman spectroscopy, and scanning electron microscopy. Significantly high amount (2 mmol g−1) of diethylenetriamine functional group (DETA) was anchored on magnetic iron oxide particles. The extraction of U(VI) from aqueous phase was studied as a function of pH of the aqueous phase, duration of the contact between Fe-DETA and aqueous phase, concentration of U(VI) in aqueous solution etc. The data on the rate of extraction of U(VI) in Fe-DETA was fitted into the first order and second order rate equations. The apparent uranium extraction capacity on Fe-DETA was determined to be 236 mg g−1, which correspond to the formation of 1:2 complex of U(VI) to diethylenetriamine ligand in Fe-DETA phase. The loaded U(VI) in Fe-DETA was quantitatively recovered using dilute Na2CO3 solution, and the recovered Fe-DETA was recycled for further extraction of U(VI), without any change in the apparent U(VI) extraction capacity.

World Trends in the Development of the Nuclear Energy Complex and their Impact on the Nuclear Industry of Ukraine

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. 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 reactorcore; 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 significance and weight of the atomic-industrial complex of Ukraine in the creation of the gross domestic product is not significant, but its role is important in ensuring economic security and achieving energy independence of the country. The state of the atomic-industrial complex in other countries of the world has been investigated. 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. The necessity of increasing the volume of uranium mining, the level of its enrichment and at the same time solving environmental issues of waste disposal has been substantiated.

A comparative study of ultra-trace-level uranium by thermal ionization mass spectrometry with continuous heating: Static and peak-jumping modes

For ensuring nuclear safeguards, we report the analytical signal-detection performance of thermal ionization mass spectrometry (TIMS) with continuous heating for the measurement of isotopic ratios in samples containing ultra-trace amounts of uranium. As methods for detecting uranium signals, peak-jumping mode using a single detector and static mode using multiple detectors were examined with U100 (10% 235U-enriched) uranium standard samples in the femtogram-to-picogram range. Uranium isotope ratios, n(235U)/n(238U), were measured down to levels of 1 fg and 3 fg in static and peak-jumping modes, respectively, while n(234U)/n(238U) and n(236U)/n(238U) values were measured down to levels of 100 fg in both modes. In addition, the dependency of the 238U signal intensity on sample quantity exhibited similar tendencies in both modes. The precisions of the isotope ratios obtained in the static mode over all sample ranges used in this study were overall slightly higher than those obtained in peak-jumping mode. These results indicate that isotope ratio measurements by TIMS with continuous heating are almost independent of the detection method, i.e., peak-jumping mode or static mode, which is characteristic of isotope-ratio measurements using the TIMS method with continuous heating. TIMS with continuous heating is advantageous as it exhibits the properties of multiple detectors within a single detector, and is expected to be used in various fields in addition to ensuring nuclear safeguards.

Sensitive detection of uranium in water samples using differential pulse adsorptive stripping voltammetry on glassy carbon electrode

Direct and rapid determination of trace amounts of uranium in natural water remains a challenge. Herein, determination of uranium by differential pulse adsorptive stripping voltammetry (DPAdSV) in presence of cupferron and diphenylguanidine on glassy carbon electrode was investigated. Under optimized conditions, the DPAdSV peak current was proportional to the concentration of uranium in the range of 3–80 μg L−1 with the detection limit of 1.0 μg L−1 and a linear correlation coefficient of 0.999. The DPAdSV method based on GCE was successfully applied to direct determination of trace uranium in natural water samples.

Reactor graphite processing in low-temperature gas-discharge plasma

Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide conversion elements, as well as fission products, which creates additional difficulties in the utilization of graphite masonry. We proposed a new method of processing, based on high-temperature separation in a nitrogen atmosphere. The processing consists in heating the radioactive graphite in an inert nitrogen atmosphere to a temperature of 2873 K, which creates the necessary conditions for the separation of radionuclides from carbon.

A chronostratigraphic framework for the Upper Jurassic Morrison Formation, western U.S.A.

ABSTRACTThe fluvial, overbank, and lacustrine deposits of the Upper Jurassic Morrison Formation of the Western Interior, U.S.A. have been intensively studied due to their diverse and well-preserved dinosaurian fauna, and the presence of economic quantities of uranium and vanadium ores. The formation crops out over 12 degrees of latitude and 1.2 million km2, and is an excellent case study for the examination of paleoecology, community structure, and evolutionary dynamics at a time in Earth's history when the climate was significantly warmer than today. However, paleoecological studies have been hampered by lack of correlation across the formation. Assuming a primarily tectonic control on fluvial architecture, we propose the first chronostratigraphic framework of the formation, which is based on sequence stratigraphy, magnetostratigraphy, and radiometric dating. The formation can be divided into three sequences each represented by a period of degradation followed by aggradation. This chronostratigraphic framework indicates that the formation youngs to the north, and was deposited over about 7 million years during the late Kimmeridgian and Tithonian. This framework provides a foundation for future sedimentological, stratigraphic, and paleobiological studies of the iconic dinosaurian fauna known from the Morrison.

RADIOLOGICAL IMPACT OF NATURAL RADIOACTIVITY IN WHITE GRANITE AT UM BAANIB AREA, SOUTHEASTERN DESERT, EGYPT

In this study, the ground spectrometric surveying shows the distribution of uranium, thorium and their ratios in the studied white granite, which reflect the addition amount of uranium to the granite from the surrounding rocks. The activity concentrations of the natural radionuclides were measured using a high-purity germanium detector (HPGe). The average activity concentration of 235U, 238U, 226Ra, 232Th and 40K was found as (27.01, 83.29, 90.08, 11.59 and 490.75 Bq/Kg) for nine white granite samples obtained from the studied area. The radium equivalent (Raeq) in Bq/Kg, external hazard index (Hex), radioactivity level index (I_γ), the absorbed dose rate (D) and the annual effective dose (AED) in outdoor environment were estimated. The annual effective dose was found to be high for all samples due to high concentration of 238U in the area under investigation which represent radiological risk for the health of population. The concentrations of major oxides (%) and trace elements (ppm) have been determined by X-ray fluorescence spectrometry. High average value for Na2O and Al2O3 which are useful in ceramics industry, high average value of Sr and Ba are useful to many important industries.

Genetic Algorithm Design of a Coupled Fast and Thermal Subcritical Assembly

This paper discusses the design of a fast spectrum subcritical assembly utilizing a genetic algorithm. The facility proposed in this paper would be a flexible platform for expanding the knowledge of fast spectrum neutron cross sections needed for next-generation fast reactor designs. The Fast Neutron Source (FNS) would be composed of both a fast and a thermal region to minimize the amount of uranium fuel and reduce overall material costs while maintaining flexibility for many potential fast neutron cross-section experiments. The FNS would be customizable and interchangeable down to 1 × 1 × 10-in.-volume sections. An optimal core design requires the adjustment of many factors to both reduce the cost and accurately reproduce the spectra of interest during an experiment. A genetic algorithm was developed to optimize this complex design problem while reducing design time and expert judgment. The genetic algorithm was able to vary multiple design factors in an unattended fashion from a random initial population of designs and arrived at a design comparable to an expertly designed assembly.

Comparison of preconcentration methods of the colloidal phase of a uranium-containing soil suspension

Three methods of membrane separation by dead-end, tangential, and centrifugal ultrafiltration (UF) were considered in order to understand the physicochemical phenomena occurring during the preconcentration of the colloidal phase of soil water. The analytical approach used involved dynamic light scattering (DLS), transmission electron microscopy (TEM), determination of total organic carbon (TOC-metry) and mass spectrometry (ICP-MS). The mass amounts of the major components of the colloidal phase, i.e. Al, Fe and total organic carbon (TOC), as well as the mass amount of uranium considered as a trace element of environmental interest, were determined, both in soil water, and in the concentrates (i.e. retentates) and filtrates of this water obtained by the 3 methods tested.Dead-end ultrafiltration led to an enlargement of the size distribution towards larger sizes because of agglomeration/aggregation phenomena. This method also generated enrichment of concentrates, in particular in organic matter. The consequence was that large structures were observed coating or embedding the particles initially present individually dispersed in the test sample. The mass amounts of elements and TOC increased more importantly than expected, which confirmed the enrichment of the concentrates from the dissolved phase probably by sorption on colloidal objects. To a lesser extent similar effects were observed after tangential ultrafiltration. Such phenomena were not observed after centrifugal ultrafiltration. From a practical point of view, both tangential and centrifugal ultrafiltration proved to be both the most practical and the best suited for the preconcentration of soil water sample. Finally, centrifugal ultrafiltration has proved to be the best compromise given the preservation of colloidal particles and method practicality.

Enhanced phytoremediation of uranium contaminated soil by artificially constructed plant community plots

In order to develop an artificially constructed plant community plot for the enhanced phytoremediation of uranium contaminated soils, three uranium accumulators including Bamboo-willow (Salix sp.), Paspalum scrobiculatum linn and Macleaya cordata were used to construct four artificial plant community plots, and greenhouse experiments were conducted to investigate the bioaccumulation of uranium by the plants and the organic acid content, enzyme activity, and the change of microbial community structure in their rhizosphere soils. The transfer factor (TF) and the total bioaccumulation amount (TBA) of uranium were used to describe remediation efficiencies in this paper. It was found that their remediation efficiencies were in the order Bamboo-willow (Salix sp.)-Paspalum scrobiculatum linn-Macleaya cordata > Bamboo-willow (Salix sp.)-Macleaya cordata > Paspalum scrobiculatum linn-Macleaya cordata > Bamboo-willow (Salix sp.)-Paspalum scrobiculatum linn. The bioaccumulation amount of uranium by each plant in the Bamboo-willow (Salix sp.)-Paspalum scrobiculatum linn-Macleaya cordata community plot was significantly (P < 0.05) higher than that by its single population, the bioaccumulation amounts of uranium by Bamboo-willow (Salix sp.), Paspalum scrobiculatum linn and Macleaya cordata were 0.29, 0.32 and 2.19 mg/plant, respectively, and they were increased by 31.82%, 77.78% and 146.07%, respectively, and the transfer efficiencies by the plants were increased by 150%, 110% and 52.17%, respectively. The interaction between the plants' roots and the microorganisms in the rhizosphere soil of the Bamboo-willow (Salix sp.)-Paspalum scrobiculatum linn-Macleaya cordata community plot resulted in the high content of organic acids such as oxalic acid in the rhizosphere soil of the plant community plot, which was significantly (P < 0.05) higher than that of its single population. The chelation of the organic acids with uranium led to an increase in the proportion of exchangeable uranium in soil solution. In addition, Burkholderia, which is an iron-producing carrier bacterium and can increase the uptake and accumulation of uranium by plants, and Leptolyngbya, which is a plant growth promoting rhizobacteria and can increase the biomass of plants, emerged in the rhizosphere soil of the plant community plot. These may be the mechanisms by which the phytoremediation of the uranium contaminated soils was enhanced by the plant community plot.

Enabling Warm-White LEDs with Very High Luminous Efficacy By Use of Uranyl Sensitized Eu3+

Warm-white light emitting diodes require a red emitting phosphor to provide sufficient emission in the red spectral region. Currently, Eu2+ activated nitrides and Mn4+ activated fluorides are state-of-the-art compounds [1,2]. Both materials have significant disadvantages: Divalent europium in nitrides suffers from a broad emission band that reaches into the NIR which strongly decreases the luminous efficacy. The synthesis of fluoride hosts for Mn4+ involves toxic hydrofluoric acid and their chemical stability is limited due to the oxidative properties of Mn4+ towards F-. Thus, Eu3+ presents an interesting alternative. Very high luminous efficacy and excellent thermal and chemical stability can be achieved in easily accessible oxide hosts [3]. However, the low absorption cross section in the UV-B to visible spectral range hinders the application of Eu3+ in warm-white LEDs. Approaches to overcome this limitation include, among others, excitation via charge transfer bands [4], sensitization with Tb3+ [5], or the use of Ce/Tb comprising core/shell materials [6]. Nonetheless, there have been no reports of successful implementation of a Eu3+ activated phosphor on a blue emitting LED chip so far. As a novel approach we chose the uranyl cation to sensitize Eu3+. While the energy transfer from uranyl to Eu3+ is well known, it has not been utilized thus far to enable Eu3+ activated red emitting LED phosphors. One reason might be that uranium is usually perceived as a health hazard for its toxicity and radioactivity. However, the dose received from ingestion of 10 mg of depleted uranium (DU) amounts to merely 1 µSv (ICRP 72), which is lower than the dose received daily through natural radiation. Consequently, to date it has not been conclusively shown if DU is a carcinogen [7,8]. With an assumed LD50 of 5 g in humans, the chemical toxicity is comparable to that of cadmium which is used in quantum dots [9]. DU would be present on an LED in minute amounts of approximately 0.1 mg per chip. The number of suitable hosts, i.e. those exhibiting both a doping site for Eu3+ and comprising the uranyl cation, is comparatively low. We studied two different compounds, Eu(UO2)3(PO4)2O(OH)∙xH2O and K4Eu2(UO2)(Ge2O7)2. The phosphate suffers from quenching due to the presence of H2O and OH moieties. Exchange of H+ by D+ was successfully attempted to alleviate this problem [10]. The germanate possesses excellent properties, allowing us to manufacture a warm-white LED employing K4Eu2(UO2)(Ge2O7)2 as the red emitter. The LED shows an excellent luminous efficacy and color rendering index at a correlated color temperature of 2700 K. To the best of our knowledge this is the first LED comprising a blue-emitting chip and a red emitting Eu3+ phosphor [11].