Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a “series” configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a “parallel” configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.

Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a “series” configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a “parallel” configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.

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.

Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a series configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a parallel configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.

Provided is a process for recovering uranium comprising (a) bringing a solution (I) into contact with a resin (I) to produce a mixture of a solution (II) and a resin (II), wherein the solution (I) is an aqueous solution that comprises 30 to 200 g/L sulfuric acid and that comprises 1 g/L to 50 g/L uranium, and wherein the resin (I) is a strong acid cation exchange resin, and (b) separating the solution (II) from the resin (II).

Provided are methods to separate an isotope from a first solution including uranium. The methods may include (a) cleaning the first solution to form a second solution including the uranium and a third solution including the isotope; (b) oxidizing the third solution to form an oxidized isotope; and (c) separating the oxidized isotope.

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 novel polymers that are grafted onto a substrate. These polymers 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 polymerisation, 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.

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).

Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a series configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a parallel configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.