A method for obtaining .sup.225AC from .sup.225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize .sup.226Ra .sup.225Ra and natural decay products therefrom; immobilizing the .sup.226Ra, .sup.225Ra, .sup.224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the .sup.225Ra with an aqueous sulfate solution to obtain a milking effluent that contains .sup.225AC. Also provided is a method for obtaining pure .sup.225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize .sup.225Ac, and natural decay products of .sup.225AC; immobilizing the .sup.225Ac, and natural decay products therefrom onto the stationary phase within the column .sup.226Ra, .sup.225Ra, .sup.224Ra; and eluting the column containing the .sup.225AC to obtain an effluent that contains the isotope parents.

One aspect of the present invention relates to a recovery method of .sup.226Ra, and the recovery method of .sup.226Ra includes a step (A1) of immersing a solid-state .sup.226Ra containing substance and a carrier having a function of adsorbing .sup.226Ra ions in a processing solution, and then irradiating the processing solution with ultrasonic waves.

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 present disclosure provides proteins that bind lanthanides and actinides. Disclosed are proteins based on lanmodulin (LanM) that comprised one or more sensitizers. Various residues in LanM may be substituted with a sensitizer, such as, for example, tryptophan. The proteins may be used to detect and quantify lanthanides and actinides. Also provided are kits and devices.

Disclosed herein are embodiments of methods for isolating rare earth elements (REEs) and radioisotopes from coal combustion products, such as fly ash. In particular embodiments, lanthanides, Al, Sc, Y, or compounds comprising lanthanides, AI, Sc, Y, or any combination thereof; or actinides can be isolated using the methods disclosed herein.

Protactinium, actinium, radium, radiolanthanides and other radionuclide fission products were separated and recovered from a proton-irradiated thorium target. The target was dissolved in concentrated HCl, which formed anionic complexes of protactinium but not with thorium, actinium, radium, or radiolanthanides. Protactinium was separated from soluble thorium by loading a concentrated HCl solution of the target onto a column of strongly basic anion exchanger resin and eluting with concentrated HCl. Actinium, radium and radiolanthanides elute with thorium. The protactinium that is retained on the column, along with other radionuclides, is eluted may subsequently treated to remove radionuclide impurities to afford a fraction of substantially pure protactinium. The eluate with the soluble thorium, actinium, radium and radiolanthanides may be subjected to treatment with citric acid to form anionic thorium, loaded onto a cationic exchanger resin, and eluted. Actinium, radium and radiolanthanides that are retained can be subjected to extraction chromatography to separate the actinium from the radium and from the radio lanthanides.

The proposed invention relates to processes of extraction and concentration of radio nuclides and can be used in radiochemical technologies when processing liquid radioactive wastes.

A method for extraction of americium from liquid radioactive wastes and its separation from rare-earth elements comprises simultaneous extraction of americium and rare-earth elements from radioactive nitrate solution with neutral solution of organic extracting agent in polar fluorinated organic solvent, washing of saturated with metals organic phase, selective re-extraction of americium. N,N,N,N-tetraalkyl-amide of diglycolic acid is used as an extracting agent and solution containing 5-20 g/L of complexon, 5-60 g/L of nitrogen-containing organic acid and 60-240 g/L of salting-out agent is used as a solution for re-extraction of americium.

Technical effect is the extraction of americium from acidic liquid radioactive solutions and its separation from all rare-earth elements in a single extraction cycle.

The present invention describes a method for purification of .sup.225Ac from irradiated .sup.226Ra-targets provided on a support comprising a leaching treatment of the .sup.225Ra-targets for leaching essentially for the entirety of .sup.223Ac and .sup.226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography for separating .sup.225Ac from .sup.226Ra and other Ra-isotops and a second extraction chromotography for separating .sup.225Ac from .sup.210Po and .sup.210Pb. The finally purified .sup.225Ac can be used to prepare compositions useful for pharmaceutical purposes.

The present invention describes a method for purification of .sup.225Ac from irradiated .sup.226Ra-targets provided on a support comprising a leaching treatment of the .sup.226Ra-targets for leaching essentially for the entirety of .sup.223Ac and .sup.226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography for separating .sup.225Ac from .sup.226Ra and other Ra-isotops and a second extraction chromotography for separating .sup.223Ac from .sup.210Po and .sup.210Pb. The finally purified .sup.225Ac can be used to prepare compositions useful for pharmaceutical purposes.