The method of separating an actinide within a mixture of an Rn-progeny alpha emitting isotope includes disposing a continuous air monitoring filter in acetone. The acetone is then evaporated, thereby forming a residue. The residue is mixed with a first solution including nitric acid, thus forming a first blend. The first blend is mixed with a second solution including an extraction solvent, thus forming a second blend. The second blend is stratified into a first layer and a second layer. The first layer is extracted from the second blend, thus separating the actinide from the Rn-progeny alpha emitting isotope.

The method of separating an actinide within a mixture of an Rn-progeny alpha emitting isotope includes disposing a continuous air monitoring filter in acetone. The acetone is then evaporated, thereby forming a residue. The residue is mixed with a first solution including nitric acid, thus forming a first blend. The first blend is mixed with a second solution including an extraction solvent, thus forming a second blend. The second blend is stratified into a first layer and a second layer. The first layer is extracted from the second blend, thus separating the actinide from the Rn-progeny alpha emitting isotope.

The use of carbamides as extractants for fully or partially separating uranium(VI) from plutonium(IV) in an aqueous solution obtained by dissolving a spent nuclear fuel in nitric acid, by method of liquid-liquid extraction, without carrying out any reduction of the plutonium(IV) to plutonium(III). The invention also relates to new carbamides. Uses are the processing of spent nuclear fuels based on uranium (especially uranium oxides—UOX) or uranium and plutonium (especially mixed uranium and plutonium oxides—MOX).

Methods and systems for the extraction of metals from an aqueous feed solution containing the metal ions. The aqueous feed solution is contacted with one side of a hydrophilic membrane support while an organic liquid is contacted with an opposite side of the hydrophilic membrane support. Metal ions migrate from the aqueous feed solution through the membrane support and into the organic liquid. The metal ions may be re-extracted from the organic liquid using a strip solution. The steps of extraction and reextraction may be carried out in a system including two hollow fiber membrane modules that each include a plurality of hydrophilic polymer hollow fibers.

The present invention provides a process for the production of a uranium trioxide yellowcake from a uranium peroxide precipitate, the peroxide precipitate being in the form of a low solids content, uranium rich feed slurry, the process including the stages of: a. thickening the feed slurry to produce a thickener underflow with a solids content in the range of 15 to 50% w/w and a thickener overflow; b. dewatering the thickener underflow to produce a solids cake with a solids content of at least 50% w/w and a dewater overflow; and c. calcining the solids cake at a temperature in the range of 450° C. to 480° C. to produce a calcined uranium trioxide yellowcake.

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.

The invention provides a method for isolating medical isotopes, the method having the steps of dissolving titanium nuclear targets to create a solution; contacting the solution with a resin so as to retain the isotopes on the resin and generate an eluent containing titanium; contacting the isotope-containing resin with acid of a first concentration to remove impurities from the resin; and contacting the isotope-containing resin with an acid of a second concentration to remove isotope from the resin.

The present invention is directed to a method for the separation of an actinide from another metal. The method comprises the following steps: (a) establishing a non-homogeneous magnetic field across a separation column containing a paramagnetic packing material and (b) providing a fluid containing the actinide and the another metal to the separation column wherein the fluid and the paramagnetic packing material are exposed to the non-homogeneous magnetic field. The non-homogeneous magnetic field is produced by a magnet having a first pole for magnetic interaction with a second pole of the magnet wherein the first pole has a different surface area than the second pole. The non-homogeneous magnetic field has a magnetic field gradient of about 500 lines/cm.sup.2/cm or more. In addition, the present invention is also directed to a method for the separation of one heavy metal from another heavy metal.

The invention provides a method for isolating medical isotopes, the method having the steps of dissolving titanium nuclear targets to create a solution; contacting the solution with a resin so as to retain the isotopes on the resin and generate an eluent containing titanium; contacting the isotope-containing resin with acid of a first concentration to remove impurities from the resin; and contacting the isotope-containing resin with an acid of a second concentration to remove isotope from the resin.

The present invention is directed to a method for the separation of an actinide from another metal. The method comprises the following steps: (a) establishing a non-homogeneous magnetic field across a separation column containing a paramagnetic packing material and (b) providing a fluid containing the actinide and the another metal to the separation column wherein the fluid and the paramagnetic packing material are exposed to the non-homogeneous magnetic field. The non-homogeneous magnetic field is produced by a magnet having a first pole for magnetic interaction with a second pole of the magnet wherein the first pole has a different surface area than the second pole. The non-homogeneous magnetic field has a magnetic field gradient of about 500 lines/cm.sup.2/cm or more. In addition, the present invention is also directed to a method for the separation of one heavy metal from another heavy metal.