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 the entirety of .sup.225Ac and .sup.226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography separating .sup.25Ac from .sup.226Ra and other Ra-isotopes and a second extraction chromatography 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 the entirety of .sup.225Ac 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 chromatography 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 invention relates to an integrated method for trivalent actinides and lanthanides separation and trivalent actinides mutual separation, which comprises: adjusting the pH value of a solution containing trivalent lanthanide and actinide ions to an appropriate value, wherein the actinide ions include americium ions and curium ions; adding an aqueous phase complexing agent, the solution is contacted with the organic phase of an extractant containing alkyl or aryl dithiophosphonic acid and nitrogen containing reagents, and actinides is extracted into the organic phase. The loaded organic phase containing actinide ions was washed by an aqueous phase with a certain pH value. The loaded organic phase is stripped with an aqueous phase of a certain pH value, and the curium ion is stripped into the aqueous phase to achieve the separation of americium and curium. The organic phase is then contacted with dilute nitric acid solution, and the americium ion in the organic phase is stripped into the aqueous phase. The invention can significantly improve the separation factor of americium and curium and reduce the operating pH value. And within the same system, the separation of trivalent actinides and trivalent lanthanides, as well as the mutual separation of trivalent actinides can be realized simultaneously through extraction and stepwise stripping, simplifying the separation process and improving separation efficiency.

The present disclosure provides a process for the separation and purification of radium and actinium from acidic solution using composite adsorbents. The process includes preparing polyoxometalates (POMs)-based mesoporous composite metal-infused resins using phosphate recovered from waste buffer solution. The resins are prepared using a modified sol-gel technique to form inorganic composite metal-oxide clusters. Embodiments of the resins include silica-coated composite metal oxide particles, including antimony-vanadium oxide particles, and tungsten-doped mesoporous titanium oxide particles. The resins have differing adsorption affinities for actinium, radium, and other metal ions and may thus be utilized for selectively separating radium and actinium from irradiated thorium targets.

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.

A method for purification of a target material for re-use in the production of radio-isotopes is disclosed, and includes obtaining a solution of irradiated target material, comprising Ra-226 and optionally Ra-225 and Ac-225, and subsequently adding an acid, being HNO3, in a predetermined quantity and providing conditions for quantitatively dissolving the target material and avoiding co-precipitation of the optionally present radio-isotopes. The method includes selectively removing H2O from the solution by distillation, leaving the acid predominantly inside the solution thereby allowing the target material to precipitate while the acid concentration in the solution increases and thereby reducing or avoiding co-precipitation of the optionally present radio-isotopes and impurities. After removal of the excess H2O, the method comprises lowering the temperature of the solution to maximize the precipitation of the target material and reduce the solubility of the target material in the remaining liquid.

A method for purifying Ac from a mixture includes Ac and at least one element selected from Ra, Pb, Po, Bi and La. The method includes the steps of: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin).

In one aspect, the technology relates to a method of producing Ac, the method including preparing a phosphate-modified titania material to produce an ion-exchange material, contacting a solution including .sup.229Th with the ion-exchange material to produce a Th-loaded titania material, eluting the Th-loaded titania material with a wash solution to produce an eluted solution containing eluted compounds including .sup.225Ac, concentrating the eluted solution to generate eluted compounds including the .sup.225Ac, and separating the .sup.225Ac from the eluted compounds.

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.