The invention relates to a beneficiation process for uranium ores comprising clay and carbonate minerals, the process comprising: performing a hydrocyclone step to obtain a hydrocyclone underflow fraction substantially comprising the uranium component; treating the hydrocyclone underflow fraction to effect a separation of carbonate and uranium minerals; and recovering the uranium-bearing minerals to produce a uranium concentrate.

Disclosed herein is a method for recovering an acid or a base during a metal extraction process. The method comprises contacting a feed stream comprising the acid or base and the metal with an ultrafiltration membrane to produce an ultrafiltration retentate and an ultrafiltration permeate, and contacting the ultrafiltration permeate with a nanofiltration membrane. The nanofiltration retentate produced comprises a majority of the metal from the feed stream, and the nanofiltration permeate produced comprises a majority of the acid or base from the feed stream. Also disclosed herein is a recovery apparatus for recovering an acid or a base during a metal extraction process.

A process is provided for recovering uranium comprising (A) bringing a solution (A) into contact with a resin (A) to produce a mixture of solution (B) and resin (B), wherein the solution (A) is an aqueous solution comprising dissolved sodium carbonate, sodium bicarbonate, or a mixture thereof, and wherein the resin (A) is a strong acid cation exchange resin that comprises one or more cationic moiety that comprises uranium and one or more cationic moiety that comprises iron, and (B) separating the solution (B) from the resin (B).

The present disclosure provides a method for numerical simulation of reactive transport during CO.sub.2+O.sub.2 in-situ leaching of uranium at a sandstone-type uranium deposit. Unlike the traditional method for numerical simulation of solute transport during in-situ leaching of uranium with consideration of only convection and diffusion, the method permits establishment of a multi-field coupled reactive solute transport model to simulate the dynamic leaching process of a sandstone-type uranium deposit in Northern China. The method provided in the present disclosure includes: creating a thermodynamic database suitable for CO.sub.2+O.sub.2 leaching of a sandstone-type uranium deposit in Northern China, and with consideration of the dynamic reaction process of uranium dissolution under combined action of oxygen O.sub.2 (aq) and bicarbonate HCO.sub.3.sup.−, performing numerical simulation of reactive transport during CO.sub.2+O.sub.2 in-situ leaching of uranium using a TOUGHREACT simulation technology framework.

Disclosed are novel polymers that contain monomer units derived from 4-vinylpyridine and monomer units derived from a co-monomer. The polymers may be complexed with a metal, and linear or crosslinked. Also disclosed are methods for preparing these polymers by radical polymerization, as well as to their use for metal capture in aqueous media, particularly uranium capture in seawater or in final nuclear waste from nuclear power plants.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

A method for extracting uranium with a coupling device of wind power generation and uranium extraction from seawater includes the following steps: adding oxygen vacancy (OV)-containing In.sub.2O.sub.3-x to absolute ethanol, and subjecting a resulting mixture to stirring and ultrasonic treatment to obtain a solution of In.sub.2O.sub.3-x in absolute ethanol; coating the solution uniformly on carbon cloth, and drying to obtain carbon cloth coated with OV-containing In.sub.2O.sub.3-x; inserting the coated carbon cloth (as a working electrode) and another blank carbon cloth (as a counter electrode) into a plastic carrier of a coupling device; fixing a small wind power generation apparatus above the plastic carrier, and connecting the working electrode and the counter electrode to a storage battery of the apparatus via wires; and placing the coupling device in seawater, and after the storage battery is charged, energizing the working electrode and the counter electrode to extract uranium from the seawater.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.