9results about "Uranium compounds" patented technology

Described herein is a process for recovering uranium tetrafluoride (UF4) from hexafluoride uranium (UF6), the process comprising dissolving UF6 directly in an ionic liquid and recovering UF4, which can be processed to obtain UO2(s) or metallic uranium.

To provide a ligand for collecting seawater uranium which can selectively collect uranium in seawater highly efficiently even at near 8 which is pH condition of seawater, a seawater uranium collection method using the ligand, and a method for producing a uranium raw material.SOLUTION: A ligand for collecting seawater uranium of the present invention is a ligand that selectively forms a metal complex with uranium in seawater, and collects the uranium, and is a compound expressed in the following general formula (1), ion derived from the compound, and one or more selected from the group consisting of polymers having the structures of the compound or the ion, where complex stability constant (logβ11) of the metal complex in seawater is 10 or more. [formula 1] (in general formula (1), R1 to R13 is as described in the text)SELECTED DRAWING: None

The application relates to the technical field of radioactive wastewater treatment, and specifically discloses a method for deep treatment and resource collaborative recovery of associated mine radioactive wastewater, which comprises the following steps: S1: ammonium metatungstate, glucose, graphene oxide and hydrochloric acid dopamine are subjected to hydrothermal reaction and calcination to obtain a base powder; S2: the base powder is subjected to template pre-assembly and hydrolysis polycondensation with soluble uranium salt, phytic acid, cyanosilane and a silicon source under weak acid conditions to obtain pre-coated powder; S3: after elution by an acid eluent, the cyan group is converted into amidoxime under weak acid microwave conditions to obtain active powder; S4: the active powder, conductive carbon black and a binder containing polyvinylidene fluoride and carboxylated carbon nanotubes are made into a composite electrode; and S5: a three-electrode system is adopted, and uranium products are recovered through cathode reduction enrichment, anode reverse desorption and precipitation calcination. The composite electrode prepared by the application can realize deep purification of uranium-containing wastewater and efficient recovery of uranium, and the recovered uranium products are high in purity.

The invention belongs to the technical field of uranium compounds, and particularly relates to a preparation method of high-purity uranyl nitrate. According to the method, the high-purity uranyl nitrate hexahydrate and uranyl nitrate trihydrate are continuously prepared by taking a ternary system phase diagram as guidance and combining a pH controlled micro-disturbance impurity removal technology and a mother liquor closed-loop circulation technology. In-situ selective removal of amphoteric impurities is achieved through accurate pH oscillation impurity removal, the impurity removal effect is enhanced in cooperation with thermal-state filtration, a target crystal phase is directionally separated out through regulation and control of a phase diagram, mother liquor after centrifugation can be directly reused for a dissolution procedure through split-flow compounding, and therefore full utilization of materials is achieved; and environmental pressure and resource waste caused by discharge of high-acidity waste liquid are avoided. The method provided by the invention ensures high purity of the product and crystal phase stability, realizes flow simplification, high-efficiency utilization of materials and zero wastewater discharge, reduces the comprehensive production cost, has good industrial suitability, and can meet the preparation requirements of high-purity raw materials such as nuclear fuel grade and the like.

The invention relates to the technical field of uranium compound metallurgy, in particular to uranyl fluoride and a preparation method thereof. The method comprises the following steps: providing uranium tetrafluoride; uranium tetrafluoride is calcined in an oxygen-containing atmosphere, so that uranyl fluoride is obtained, and the oxygen-containing atmosphere comprises oxygen and ozone. According to the method, one-step direct conversion is achieved, operation is easy, control is easy, automatic and continuous production is achieved, and high-purity uranyl fluoride can be obtained.

The invention relates to the technical field of in-situ leaching uranium mining, and provides a method for reducing silicon dioxide in in-situ leaching uranium mining closed cycle system diuranate, which comprises the following steps: controlling silicon dioxide accumulation: reducing the water passing amount of leachate to be less than 340 cubic meters per hour, shortening the single operation period of an adsorption tower to be within 30 days, and switching to a standby adsorption tower after expiration; removing residual silicon dioxide: conveying the resin by adopting compressed air, controlling the conveying pressure to be 0.25-0.3 MPa, carrying out reverse flushing in the conveying process, then transferring the resin to a leaching tower, and pre-flushing with clear water; and carrying out vibration cleaning on the pre-flushed resin to remove residual silicon-containing silt. Through physical control of a main process chain of accumulation control, residue removal and fine matter removal, the content of silicon dioxide in the diuranate product is reduced from the source, the problems that the product adheres to a barrel, discharging is difficult, the quality exceeds the standard and operation safety is poor are solved, and cost reduction and efficiency improvement are achieved.

The present invention relates to a method for preparing targets for the production of radioisotopes or nuclear fuels, comprising a reactive sintering step. (no figures)

This invention discloses an electrochemical uranium extraction system and a method for preparing molybdenum oxide-based nanosheets for electrochemical uranium extraction, comprising: Step 1, synthesizing MoO x Nanosheets; Step 2: Using a uranium source and the MoO prepared in Step 1 x U-MoO was synthesized using nanosheets as raw materials. x Nanosheets. This invention successfully introduces isolated uranyl into MoO. x Nanosheets were used to extract uranium from uranium-containing wastewater, achieving highly efficient electrochemical reduction and deposition of uranium in fluorine-containing wastewater. During electrolysis, isolated uranyl-MoO₂... x This creates an interfacial hydrogen spillover effect, enabling the regeneration of uranium active sites and ensuring the continuous reduction and deposition of uranyl. Furthermore, when combined with an electrochemical uranium extraction system, it can also achieve uranium extraction in seawater or other uranium-containing wastewater.

The invention discloses an eggshell type catalyst based on a flame method, a preparation method of the eggshell type catalyst and application of the eggshell type catalyst to preparation of tetravalent uranium through catalytic reduction of hexavalent uranium, and belongs to the field of nuclear fuel aftertreatment. According to the technical scheme, firstly, hydrophobic treatment is conducted on the carrier, then absolute ethyl alcohol is added to the carrier and ignited, a metal salt solution is sprayed to a flame area in the combustion process, the metal salt solution is rapidly evaporated and fixed on the surface of the carrier through heat generated by flames, and an extremely thin active component shell layer is formed on the outer surface of the carrier; and finally, carrying out reduction treatment to obtain the eggshell type catalyst. The preparation method is simple, only the precursor salt solution is needed, the problem that competitive adsorbents are added in the traditional eggshell type catalyst preparation process is avoided, the catalyst is applied to the reaction process for preparing tetravalent uranium through catalytic reduction of hexavalent uranium, and the method has the advantages of being high in metal utilization rate, mild in reaction condition and low in cost. The method has the advantages of high conversion rate of tetravalent uranium and high utilization rate of the reducing agent, and has important industrial application value.