28 results about "Uranyl" patented technology

A method for predicting in-situ leaching effects of sandstone-type uranium mining deposits after blasting is provided, which comprises: based on a finite element analysis platform, establishing an HJC rock-blasting constitutive model, and carrying out a blasting numerical simulation; calibrating a cloud map of blasting crack damage by using a Kriging interpolation algorithm; establishing a COMSOL multiphysics model; establishing a coupling interface between the COMSOL multiphysics model and PHREEQC based on MATLAB, and optimizing a cycle duration and a time step; performing a geochemical reaction calculation and saving results, running COMSOL files, and inputting the results of geochemical reaction calculation into PHREEQC to obtain a dynamic cyclic iterative simulation; dynamically correcting migration coefficients of uranyl complexes by integrating an LSTM neural network, and stopping the cycle to output multi-scale dynamic simulation results of migration of uranium.

The invention discloses a method for quantitatively detecting uranyl ions by adopting a silicon-based carbon dot material and application of the method, and belongs to the field of nano composite materials and radionuclide detection. Mixing the silicon-based carbon dot composite material with an acid solution containing uranyl ions, carrying out ultrasonic treatment, detecting the fluorescence intensity of the mixed solution by adopting a fluorescence spectrum, and quantitatively analyzing the uranyl ion concentration according to the uranyl ion concentration and a fluorescence intensity curve. The silicon-based carbon dot composite material is a silicon-based carbon dot material of which the surface is modified by functional groups; the functional groups comprise hydroxyl, carboxyl and amino. The method can generate stable fluorescence response change when acting with uranyl ions, accurate quantitative analysis of uranyl ion concentration can be realized, the silicon-based carbon dot composite material has high uranyl ion detection response speed by means of the synergistic effect of the nanoscale effect and the surface functional group, and detection can be completed in a short time.

The application belongs to the technical field of ion detection, and particularly relates to a preparation method of a rapid detection uranyl ion ratio type fluorescent probe, comprising the following steps: dissolving rhodamine B and phosphorus oxychloride in 1,2-dichloroethane to obtain product 1; dissolving the product 1 in acetonitrile, adding 2-aminobenzimidazole and triethylamine, and stirring under heating; after the reaction is completed, column chromatography purification is carried out, and vacuum drying is carried out to obtain the target product fluorescent probe RBN; and the fluorescent probe RBN is dissolved in DMSO to prepare a mother liquor. The fluorescent probe has the advantages of rapid response to uranyl ions, simple synthesis route, simple detection equipment and method, and the like, and can be used for qualitative and quantitative detection of uranyl ions in an environment and a biological system.

This invention discloses a purification method for producing molybdenum-99 in a reactor using uranyl nitrate solution as nuclear fuel, relating to the field of radioisotope production technology. The method involves first adding an oxidant to the crude molybdenum-99 product solution produced by the solution reactor, oxidizing the crude molybdenum-99 product to MoO4. 2‑ The solution is then evaporated to dryness; a digestion solution is added to the evaporation residue to dissolve the impurities; a dissolving solution is added to the digested solid to dissolve the solid, which is then evaporated to dryness; finally, an alkaline solution is added to the evaporated solid to dissolve it, yielding a molybdenum-99 product solution that meets pharmacopoeia requirements. Compared to traditional methods for purifying molybdenum, this invention does not introduce new impurities, has a low heating temperature, low energy loss, is easy to operate in a hot chamber, and has a high impurity removal rate.

This invention discloses a biosensor for detecting uranyl ions using a test strip, comprising a reaction system and a test strip. The reaction system includes a DNAzyme substrate chain and a DNAzyme enzyme chain. The test strip includes a substrate and a sample pad, a coupling pad, a nitrocellulose membrane, and an absorbent pad sequentially overlapped on the substrate. A gold nanoparticle-DNA probe I complex is immobilized on the coupling pad. A test line and a control line are provided on the nitrocellulose membrane. An SA-biotin-DNA probe II is immobilized on the test line, and an SA-biotin-DNA probe III is immobilized on the control line. Compared with existing technologies, this biosensor integrates a DNase-induced cleavage reaction with gold nanoparticle-mediated colorimetric detection technology, achieving high sensitivity and high specificity detection of uranyl ions. Furthermore, the detection process is simple and rapid, providing a solution for detecting UO2 in environmental and biological samples. 2+ This provides important technical support for on-site monitoring.

The invention relates to a biosensor, a kit and a detection method for rapidly and highly sensitively detecting uranyl ions. According to the biosensor, a four-leaf clover-shaped rolling loop mediated quadruple Walker is adopted as a signal amplifier to amplify a signal to detect UO2 < 2 + >; the four-leaf clover-shaped rolling loop mediated quadruple Walker comprises an L1 / L2 / L3 / L4 / Asist compound, a UO2 < 2 + > dependent DNAzyme substrate chain, a streptavidin modified magnetic bead and a buffer solution. In the presence of UO2 < 2 + >, the activated Walker can circularly cut a fluorescently-labeled substrate chain to generate an amplified fluorescence signal, so that high-sensitivity and high-specificity detection of UO2 < 2 + > is realized.

The invention discloses an irradiation modification method of precious metal nano-enzyme and application of the irradiation modification method, and belongs to the technical field of nano-enzyme modification.The method comprises the steps that the precious metal nano-enzyme is prepared and dried; irradiating the dried noble metal nano-enzyme, and controllably introducing vacancy, dislocation, grain boundary or amorphous region defects by selecting irradiation source types and regulating irradiation energy and dose to obtain irradiation modified noble metal nano-enzyme; the method is different from a traditional nano-enzyme chemical modification method, the defects of the nano-enzyme are regulated by adopting physical irradiation, impurities are prevented from being introduced into a chemical reagent, the defect density is controllable, and the peroxidase-like activity of the obtained irradiation modified noble metal nano-enzyme is remarkably enhanced compared with that of an unirradiated sample; good application prospects are shown in the fields of uranyl ion detection and the like.

The invention discloses an acid-resistant loose nanofiltration membrane as well as a preparation method and application thereof, and belongs to the technical field of water treatment membranes. According to the preparation method, 3, 5-diaminobenzoic acid (DABA) is taken as a water-phase monomer and is subjected to interfacial polymerization with 1, 3, 5-trimesoyl chloride (TMC) on the surface of an ultrafiltration bottom membrane, and the acid-resistant loose nanofiltration membrane is obtained. Carboxyl contained in DABA can reduce the reaction activity of amino and acyl chloride groups in TMC and provide certain steric hindrance, and formation of a loose polyamide network structure is facilitated; meanwhile, the acid resistance of the nanofiltration membrane is enhanced by the contained whole aromatic rings. The prepared loose nanofiltration membrane can efficiently and selectively separate uranyl ions / coexisting inorganic ions under acidic and alkaline conditions, and shows excellent anti-pollution performance. The preparation method provided by the invention is simple in process and easy to operate, and the prepared acid-resistant loose nanofiltration membrane has potential application value for treating actual radioactive spent fuel post-treatment wastewater.

The invention belongs to the technical field of nuclear fuel development, and particularly relates to a preparation method of a large-grain UO2 fuel pellet. The preparation method comprises the following steps: (1) uniformly mixing a grain growth substance and an acid-deficient uranyl nitrate solution, adding saturated ammonium carbonate or introducing reaction gas for precipitation reaction to generate an AUC precipitate; the reaction gas is a mixture of NH3 and CO2; (2) filtering the AUC precipitate to obtain a filter cake, and washing, filtering, drying and calcining to obtain powder; (3) granulating the powder, and forming to obtain a green fuel pellet; and (4) sintering the green fuel pellet to obtain the large-grain UO2 fuel pellet. The average grain size of the prepared large-grain UO2 fuel pellet is larger than or equal to 40 micrometers, and the large-grain UO2 fuel pellet has the high melting point, good water corrosion performance and irradiation stability of traditional UO2 fuel and further has the low fission gas release rate and the high heat conductivity.

The present application relates to a kind of graphene aerogel and its preparation method and application, first, in strong oxidizing acidic system, expandable graphite is prepared epoxy type graphite oxide by controllable oxidation;The prepared epoxy type graphite oxide is sol-gel treatment with L-cysteine and 2,5-diaminobenzonitrile organic functional monomer, it is converted into graphene hydrogel material with three-dimensional structure by heat treatment;Using hydroxylamine hydrochloride, the prepared three-dimensional graphene hydrogel is oxidized, and nitrile group is converted into amidoxime group;Graphene hydrogel material with amidoxime group and amino group is dried, and graphene aerogel for adsorbing uranyl ion in radioactive wastewater is obtained.The preparation method of the present application is simple and feasible, the obtained graphene aerogel has high adsorption performance and selectivity, and can efficiently adsorb and remove uranyl ion from radioactive wastewater.

The application discloses a purification method for producing iodine-131 by a reactor with a uranyl nitrate solution as nuclear fuel, and comprises the following steps: adding a reducing agent into a crude iodine-131 product solution to reduce sodium iodine-131 into iodine-131 element; distilling the iodine-131 element to obtain iodine-131 element vapor; and absorbing the iodine-131 element vapor by using an alkaline solution to obtain a sodium iodine-131 solution product. The purification method can effectively remove radioactive impurities in the iodine-131 extracted from the reactor with the uranyl nitrate solution as the nuclear fuel, and can obtain the sodium iodine-131 solution product meeting the medical requirements. The purification method for the iodine-131 isotope is simple, and can effectively remove the impurities in the iodine-131 isotope, so that the iodine-131 isotope meets the medical requirements, and the average recovery rate of iodine can reach more than 90%.

This invention discloses a purification apparatus and method for iodine-131 produced by a nuclear reactor using uranyl nitrate aqueous solution as fuel, relating to the field of radioactive isotope production technology. The apparatus includes a carrier gas cylinder, an evaporator, a waste liquid tank, a primary absorption tank, a secondary absorption tank, a tertiary absorption tank, and a product tank. The carrier gas cylinder is connected to the evaporator via an inlet pipe. A liquid inlet is located at the top of the evaporator. An outlet pipe is connected to the top of the evaporator, connecting to the primary absorption tank. The primary absorption tank is connected to the secondary absorption tank via a pipe, and the secondary absorption tank is connected to the tertiary absorption tank via a pipe. Discharge pipes are connected to the bottom of the primary, secondary, and tertiary absorption tanks, and these pipes are all connected to the product tank. The bottom of the evaporator is connected to the waste liquid tank via a drain pipe. This apparatus and method achieve high product recovery and high product purity after iodine-131 purification. 131 The sodium hydroxide solution product meets the requirements of medical technical specifications.

The invention discloses a preparation method of a UiO-66-NH-(AO) (at) CdZnS2 composite material, the UiO-66-NH-(AO) (at) CdZnS2 composite material obtained by the invention has excellent extraction and removal capabilities on uranyl ions in a water body, and the removal rate of 95.9% of the uranyl ions in the water body can be realized within a short time (2h); meanwhile, multiple and efficient reuse can be achieved, and after five times of circulation, 95.03% of the removal rate of uranyl ions in water can still be achieved.

The application discloses a preparation method of a sulfonic acid-based porous organic polymer and application of the sulfonic acid-based porous organic polymer in adsorption of uranyl ions and trace metal ions. The preparation method comprises the following steps: firstly, benzylization modification is conducted on a cyclodextrin to obtain a benzylated cyclodextrin monomer; then, the benzylated cyclodextrin monomer is subjected to a Friedel-Crafts alkylation polymerization reaction with a linker under catalysis of a catalyst to construct a porous organic polymer with high crosslinking degree; and finally, chlorosulfonic acid is used for sulfonation modification to introduce high-density sulfonic acid group active sites. The obtained polymer combines the host-guest recognition ability of the cyclodextrin and the rapid mass transfer effect of the porous skeleton, and exhibits extremely fast adsorption kinetic response and excellent adsorption capacity. The material has simple preparation process and high stability, and is especially suitable for superfast extraction of ultra-low-concentration uranyl ions in seawater.

The application belongs to the technical field of preparation of adsorption separation functional materials, and relates to a method for preparing a polyvinyl phosphonic acid grafted enzyme fixed magnetic nanochain adsorbent by droplet confinement, and high-efficiency uranium adsorption application of the adsorbent. The application can construct the effective uranium ion trap in the continuous water phase of the high internal phase emulsion through the space limited conjugation of the enzyme fixed magnetic nanochain and the polyvinyl phosphonic acid polymer. The polyvinyl phosphonic acid polymer is grown from the surface of a model enzyme, i.e. alpha-chymotrypsin, by using a novel water-soluble atom transfer radical polymerization (ATRP) initiator, and provides high-density accessible phosphonic groups for capturing uranium ions, so that the polyvinyl phosphonic acid polymer and the enzyme fixed magnetic nanochain adsorbent with uniform surface functional sites are prepared, and are applied to high-efficiency adsorption of uranium cation.

The application discloses a ratio type fluorescent probe for detecting uranyl ions and a preparation method thereof. The method comprises the following steps: (1) preparing a metal-organic framework material Tb-TPA by taking Tb as a metal center and terephthalic acid (TPA) as an organic ligand; (2) preparing a metal-organic framework material Eu-TMTPA by taking Eu as a metal center and tetramethoxy terephthalic acid (TMTPA) as an organic ligand; and (3) mixing the Tb-TPA and the Eu-TMTPA according to a mass ratio of 1:0.5-3 to obtain the ratio type fluorescent probe. The prepared ratio type fluorescent probe can be used for detecting uranyl ions and has the characteristics of fast response speed, good selectivity and high sensitivity. The probe has a Tb and Eu double emission system, the addition of uranyl ions has no influence on the luminescence of the Tb-TPA, can quench the luminescence of the Eu-TMTPA, thereby realizing ratio type fluorescent analysis, and through self-calibration of two luminescence wave bands, can greatly eliminate or reduce the interference of irrelevant factors of the uranyl ions, and improve the detection sensitivity and accuracy.

The application relates to the technical field of functional nanocomposites and photocatalytic uranium extraction, and particularly discloses a ZAIS@NH2-MIL-101(Fe) photocatalytic material, a preparation method and application thereof. The method is characterized in that: firstly, ZAIS quantum dots are prepared through mercapto ligand assisted zinc doping; and then the ZAIS quantum dots are combined with NH2-MIL-101(Fe) through reverse solvent induced self-assembly to form a tight heterojunction. The obtained composite material has the porous adsorption enrichment capacity of NH2-MIL-101(Fe) and the photocatalytic performance of the ZAIS quantum dots, and can synergistically improve the capture and photocatalytic reduction efficiency of complex uraniumyl ions in seawater or simulated seawater and other complex water bodies, thereby providing a new material for efficient seawater uranium extraction.

The invention relates to the technical field of U (VI)-containing waste liquid treatment, in particular to a synthesis method, a product and application of oxygen vacancy defect cuprous oxide. The synthesis method of the oxygen vacancy defect cuprous oxide comprises the following steps: mixing copper chloride, LiCl and CaCl2, and calcining to obtain a product A; and dispersing the product A in water, adding an alkali solution, stirring, centrifuging, washing, and drying to obtain the oxygen vacancy defect cuprous oxide. The cuprous oxide is synthesized in the fused salt, a reducing agent is not needed, and the method is green and environment-friendly; the synthesis conditions are economical and convenient. The cuprous oxide prepared by the synthesis method has the oxygen vacancy defect; the cuprous oxide has an oxygen vacancy defect, so that the cuprous oxide has a very good removal effect on uranyl ions in water, and a foundation is laid for removal of uranyl ions in water.

The application discloses a glycosylated hydroxypyridinone ligand and a preparation method and application thereof. The glycosylated hydroxypyridinone ligand has excellent coordination capacity with uranium ions, thorium ions and the like, and can realize optimization of the decontamination effect under single administration through intraperitoneal or tail vein administration, and has extremely application prospects in preparation of actinide decontamination agents. Meanwhile, the preparation method is simple, the synthesis condition is mild, and the yield is high, and is suitable for large-scale production.

The invention discloses a uranyl ion fluorescent probe as well as a preparation method and application thereof, and belongs to the technical field of preparation of probes. The molecular formula of the probe is C36H27N2O6S +, according to the preparation method, 2-aminothiophenol, 2, 4-dihydroxy benzaldehyde, sodium pyrosulfite, phthalic anhydride and 3-acetyl-7-(diethylamino)-2H-benzopyran-2-ketone are taken as raw materials, the probe is prepared through three-step reaction, the molar ratio of key raw materials in each step is definite, and the synthesis process is simple. The probe is used for detecting uranyl ions in a water environment, the fluorescence spectrum of the probe is enhanced at 490 nm and weakened at 700 nm under excitation of 400 nm, the response time is about 20 minutes, the lower detection limit reaches 1.36 * 10 <-7 > mol / L, and the probe can resist interference of various metal ions, anions and small biological molecules and has the advantages of rapidness, sensitivity and good selectivity.

The application discloses an oxygen-enriched vacancy tungsten trioxide / carboxylated multi-walled carbon nanotube composite electrode material and a preparation method and application thereof in adsorbing uranium. The tungsten chloride is used as a precursor, is dissolved in a reducing agent ethanol through ultrasonic treatment, carboxylated multi-walled carbon nanotubes are added to enhance the conductivity of the electrode material, and the carboxylated multi-walled carbon nanotubes are dispersed through ultrasonic treatment again. Finally, the oxygen-enriched vacancy tungsten trioxide / carboxylated multi-walled carbon nanotube composite electrode material WO 3‑x / MWCNTs-COOH is synthesized through a solvothermal reaction. The oxygen-enriched vacancy tungsten trioxide / carboxylated multi-walled carbon nanotube composite electrode material prepared by the application can reach an adsorption capacity of 107.6 mg·g ‑1 -1 for uranium at pH=4. The uranium ion is quickly adsorbed and saturated, the adsorption capacity of the electro-adsorption reaches 1.2 times of the adsorption capacity under the condition of no power supply, and the required time is only 2 / 5 of the static adsorption.

The invention relates to the technical field of waste liquid detection, and particularly discloses a graphene uranyl ion sensor material as well as a preparation method and application thereof. The preparation method comprises the following steps: 1) compounding COQDs and UiO-66-NH2 < + > type MOF to form COQDs (at) MOF; and 2) carrying out surface functional modification on the COQDs (at) MOF by using 8-hydroxyquinoline to obtain the GQDs (at) MOF (at) 8-HQ composite material. By optimizing the preparation process, high-sensitivity and high-selectivity detection of uranyl ions is realized, so that the sensor has the advantages of low detection limit, wide linear range, high photobleaching resistance and the like, can be effectively applied to detection of low-concentration uranyl ions, and provides a new technical means for environmental monitoring and nuclear waste management.

The invention discloses a preparation method and application of an MOF-derived core-shell heterojunction fabric. The preparation method specifically comprises the following steps: (1) carrying out electron beam irradiation treatment on a fabric; (2) mixing quantum dots, 2-methylimidazole, organic amine and a reaction solvent, and performing ultrasonic dispersion to obtain a solution A; adding zinc salt into the reaction solvent to obtain a solution B; the solution A and the solution B are sequentially and alternately dropwise added to the surface of a fabric, finally, the fabric is completely soaked in the solutions, stirring is conducted at the room temperature, then heating is conducted, and a quantum dot (at) MOF fabric material is obtained; and (3) adding a sulfur precursor into the solution containing the quantum dot (at) MOF fabric material in the step (2), continuously carrying out heating reaction at the heating temperature in the step (2), taking out the fabric after the reaction, and cleaning and drying to obtain the quantum dot (at) ZnS fabric. The method disclosed by the invention is low in energy consumption, and the obtained material can quickly reduce uranyl ions (UO2 < 2 + >) in a water body under an illumination condition.

The invention provides a uranyl nitrate solution reactor passive hydrogen-oxygen recombiner, and belongs to the technical field of medical isotope reactors. The device comprises a device shell with one closed end. A gas inlet is formed in the open end of the device shell; an inlet heater communicated with the gas inlet is arranged in the device shell, and the other end of the inlet heater is sequentially connected with a front honeycomb catalyst and a rear honeycomb catalyst; a certain space is reserved between the side walls of the inlet heater, the front honeycomb catalyst and the rear honeycomb catalyst and the inner wall of the device shell to serve as a gas channel; a flow guide plate is arranged on the side wall of the tail part of the rear honeycomb catalyst, and a certain distance is reserved between the flow guide plate and the inner wall of the device shell; and a gas outlet communicated with the space is formed in one side of the end part of the device shell. The uranyl nitrate solution reactor passive hydrogen-oxygen recombiner provided by the invention can ensure safe and stable operation of the reactor, and is high in integration degree, simple in system structure and convenient to overhaul and maintain.