Disclosed herein are systems, methods, processes, and apparatuses for treating radioactive waste, through systems designed to bind and dry radioactive media. In some of its various embodiments, the system includes at least one helical screw designed to receive and mix liquid wastes with ion exchange media, as well as convey the resulting slurry through one or more of a binding, dewatering, and drying/off-gassing region.

Provided is a method for producing ultrapure water to supply, to a use point, ultrapure water obtained by treating raw material water for ultrapure water production in an ultrapure water production apparatus, wherein the raw material water for ultrapure water production contains at least one or more elements selected from B, As, Al, Ti, Cr, Fe, Cu, Zn, Sn, V, Ga, and Pb, and wherein an ion exchanger-filled module filled with at least a monolithic organic porous anion exchanger is installed in a treatment path of the ultrapure water production apparatus or in a transfer path from the ultrapure water production apparatus to the use point, and water to be treated is passed through the ion exchanger-filled module for treatment.

To provide a filter capable of efficiently removing metal ions in a treatment liquid, and capable of easily obtaining a solution having an extremely low metal ion content. A depth filter includes a porous molded article. The porous molded article is a sintered material of mixed powder or a swollen material of the sintered material. The mixed powder contains dried gel powder and thermoplastic resin powder. The dried gel powder contains an ion exchange resin including a sulfonic acid group, and a nitrogen-containing chelating resin.

To provide a filter capable of efficiently removing metal ions in a treatment liquid, and capable of easily obtaining a solution having an extremely low metal ion content. A depth filter includes a porous molded article. The porous molded article is a sintered material of mixed powder or a swollen material of the sintered material. The mixed powder contains dried gel powder and thermoplastic resin powder. The dried gel powder contains an ion exchange resin including a sulfonic acid group, and a nitrogen-containing chelating resin.

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.

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.

A filter includes a porous molding, the porous molding being a sintered product of mixed powder containing dry gel powder including an ion exchange resin and thermoplastic resin powder, or a swelled body of the sintered product. When water having an electric resistivity value of 18 MΩ.Math.cm or more is allowed to pass through a space velocity of 1200 hr−1, the electric resistivity value of water after passage is 15 MΩ.Math.cm or more. To provide a filter that can efficiently remove metal ions in a solution to be treated, and easily acquire a solution having an extremely low content of metal ions.

A filter includes a porous molding, the porous molding being a sintered product of mixed powder containing dry gel powder including an ion exchange resin and thermoplastic resin powder, or a swelled body of the sintered product. When water having an electric resistivity value of 18 MΩ.Math.cm or more is allowed to pass through a space velocity of 1200 hr−1, the electric resistivity value of water after passage is 15 MΩ.Math.cm or more. To provide a filter that can efficiently remove metal ions in a solution to be treated, and easily acquire a solution having an extremely low content of metal ions.

Chemically inert, mechanically tough, cationic metallo-polyelectrolytes designed as durable anion-exchange membranes (AEMs) via ring-opening metathesis polymerization (ROMP) of cobaltocenium-containing cyclooctene with triazole as the only linker group, followed by backbone hydrogenation to provide a new class of AEMs with a polyethylene-like framework and alkaline-stable cobaltocenium cation for ion transport, which exhibit excellent thermal, chemical and mechanical stability, as well as high ion conductivity.

Chemically inert, mechanically tough, cationic metallo-polyelectrolytes designed as durable anion-exchange membranes (AEMs) via ring-opening metathesis polymerization (ROMP) of cobaltocenium-containing cyclooctene with triazole as the only linker group, followed by backbone hydrogenation to provide a new class of AEMs with a polyethylene-like framework and alkaline-stable cobaltocenium cation for ion transport, which exhibit excellent thermal, chemical and mechanical stability, as well as high ion conductivity.