C22B60/00

METHOD FOR SEPARATING RADIONUCLIDES FROM ORES, ORE CONCENTRATES, AND TAILINGS
20240263274 · 2024-08-08 ·

A method for separating radionuclides from ores, ore concentrates, and tailings or mixtures of two or more thereof comprising the steps of (a) providing an ore, ore concentrate, or tailings, or a mixture of two or more thereof in which radionuclides have been liberated onto surfaces of particles of the ore, ore concentrate or tailings or mixtures of two or more thereof, (b) forming a pulp or slurry comprising the ore, ore concentrate or tailings or a mixture or two or more thereof from step (a), water or an aqueous solution, and an ion exchange resin to cause the radionuclides to load onto the resin, and (c) separating the resin from other solids present in the pulp or slurry.

METHOD FOR SEPARATING RADIONUCLIDES FROM ORES, ORE CONCENTRATES, AND TAILINGS
20240263274 · 2024-08-08 ·

A method for separating radionuclides from ores, ore concentrates, and tailings or mixtures of two or more thereof comprising the steps of (a) providing an ore, ore concentrate, or tailings, or a mixture of two or more thereof in which radionuclides have been liberated onto surfaces of particles of the ore, ore concentrate or tailings or mixtures of two or more thereof, (b) forming a pulp or slurry comprising the ore, ore concentrate or tailings or a mixture or two or more thereof from step (a), water or an aqueous solution, and an ion exchange resin to cause the radionuclides to load onto the resin, and (c) separating the resin from other solids present in the pulp or slurry.

Metal ION Recovery from a Bound Chelate/Sequestering-Agent Solution
20240309490 · 2024-09-19 ·

Methods for the recovery of metal ions from an aqueous metal-chelator solution are disclosed. In some embodiments, a method includes dissociating a metal ion from a chelating agent to form a free chelating agent and then precipitating or removing the free chelating agent, wherein at least some of the metal ions remain in an acid solution for further processing. For example, the metal ions can be used in other applications, such as in medical applications and industrial applications.

Metal ION Recovery from a Bound Chelate/Sequestering-Agent Solution
20240309490 · 2024-09-19 ·

Methods for the recovery of metal ions from an aqueous metal-chelator solution are disclosed. In some embodiments, a method includes dissociating a metal ion from a chelating agent to form a free chelating agent and then precipitating or removing the free chelating agent, wherein at least some of the metal ions remain in an acid solution for further processing. For example, the metal ions can be used in other applications, such as in medical applications and industrial applications.

Processes for the recovery of uranium from wet-process phosphoric acid using dual or single cycle continuous ion exchange approaches

In alternative embodiments, the invention provides processes and methods for the recovery, removal or extracting of, and subsequent purification of uranium from a wet-process phosphoric acid using a continuous ion exchange processing approach, where the uranium is recovered from a phosphoric acid, or a phos-acid feedstock using either a dual or a single stage extraction methodology. In both cases an intermediate ammonium uranyl-tricarbonate solution is formed. In alternative embodiments, in the dual cycle approach, this solution is contacted in a second continuous ion exchange system with a strong anion exchange resin then subsequently recovered as an acidic uranyl solution that is further treated to produce an intermediate uranyl peroxide compound which is ultimately calcined to produce the final uranium oxide product. In alternative embodiments, in the single cycle case, the intermediate ammonium uranyl-tricarbonate solution is evaporated to decompose the ammonium carbonate and produce an intermediate uranium carbonate/oxide solid material. These solids are digested in an acid medium, and then processed in the same manner as the secondary regeneration solution from the dual cycle process to produce an intermediate uranyl peroxide that is calcined to produce a final uranium oxide product.

Use of an organic-inorganic hybrid material for extracting uranium(VI) from a sulfuric acid aqueous solution, issued notably from the sulfuric leaching of a uranium-bearing ore

The invention relates to the use of an organic-inorganic hybrid material, comprising an inorganic solid support on which are grafted organic molecules having the general formula (I) below: ##STR00001##
in which: x, y and z=0 or 1, with at least one of x, y and z different from 0; m=1 to 6; v and w=0 or 1, with v=1 when w=0, and v=0 when w=1; if x=0, R.sup.1H or a saturated or unsaturated, linear or branched, C.sub.1 to C.sub.12 hydrocarbon group, whereas, if x=1, R.sup.1=a group bound to the inorganic solid support by at least one covalent bond; if y=0, R.sup.2H or a saturated or unsaturated, linear or branched, C.sub.1 to C.sub.12 hydrocarbon group, whereas, if y=1, R.sup.2=a group bound to the inorganic solid support by at least one covalent bond; if z=0, R.sup.3H or a saturated or unsaturated, linear or branched, C.sub.1 to C.sub.12 hydrocarbon group, whereas, if z=1, R.sup.3=a group bound to the inorganic solid support by at least one covalent bond; R.sup.4 and R.sup.5H, a saturated or unsaturated, linear or branched, C.sub.2 to C.sub.8 hydrocarbon group, or a monocyclic aromatic group;
for extracting uranium(VI) from a sulfuric acid aqueous solution. The invention also relates to a method that makes it possible to recover the uranium(VI) present in a sulfuric acid aqueous solution, selectively with respect to the other metal cations that may also be present in said solution.

Extraction of uranium from wet-process phosphoric acid

A system for extracting uranium from wet-process phosphoric acid (WPA), includes an ion exchange resin or solvent extractor for separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. An ion exchange resin is positioned to receive the loaded uranium solution stream and bind uranium species thereto. An anion solution stream is positioned to feed a solution comprising anions onto the ion exchange resin to form a loaded uranium eluant stream. The loaded uranium eluant stream may then be treated to provide a uranium containing product.

RECOVERING MULTIPLE ELEMENTS FROM AQUEOUS STREAMS

A system and method of extracting elements from an aqueous stream are described herein. The method includes designing a process to extract at least two elements from the aqueous product stream. The at least two elements have different commercial values. The process is optimized to minimize a cost of extracting the at least two elements and to maximize a value of extracting the at least two elements. The method further includes extracting the at least two elements according to the process.

RECOVERING MULTIPLE ELEMENTS FROM AQUEOUS STREAMS

A system and method of extracting elements from an aqueous stream are described herein. The method includes designing a process to extract at least two elements from the aqueous product stream. The at least two elements have different commercial values. The process is optimized to minimize a cost of extracting the at least two elements and to maximize a value of extracting the at least two elements. The method further includes extracting the at least two elements according to the process.

Processes for the recovery of uranium from industrial phosphoric acid using dual or single cycle continuous ion exchange approaches

In alternative embodiments, the invention provides processes and methods for the recovery, removal or extracting of, and subsequent purification of uranium from a wet-process phosphoric acid using a continuous ion exchange processing approach, where the uranium is recovered from a phosphoric acid, or a phos-acid feedstock using either a dual or a single stage extraction methodology. In both cases an intermediate ammonium uranyl-tricarbonate solution is formed. In alternative embodiments, in the dual cycle approach, this solution is contacted in a second continuous ion exchange system with a strong anion exchange resin then subsequently recovered as an acidic uranyl solution that is further treated to produce an intermediate uranyl peroxide compound which is ultimately calcined to produce the final uranium oxide product. In alternative embodiments, in the single cycle case, the intermediate ammonium uranyl-tricarbonate solution is evaporated to decompose the ammonium carbonate and produce an intermediate uranium carbonate/oxide solid material. These solids are digested in an acid medium, and then processed in the same manner as the secondary regeneration solution from the dual cycle process to produce an intermediate uranyl peroxide that is calcined to produce a final uranium oxide product.