Abstract: An extractant which makes it possible to extract both light rare earths and heavy rare earths from an aqueous phosphoric acid solution, likely to be present in this solution, and which is characterised in that it comprises: a compound of formula (I) below: wherein R1 and R2, identical or different, are a hydrocarbon group, saturated or unsaturated, linear or branched, in C6 to C12; R3 is a hydrocarbon group, in C1 to C6, or a hydrocarbon group, saturated or unsaturated, monocyclic, in C3 to C8; R4 and R5, identical or different, are a hydrogen atom or a hydrocarbonate group, saturated or unsaturated, linear or branched, in C2 to C8; and a surfactant. Applications of this extractant include treatment of aqueous solutions from the leaching of natural phosphates by sulphuric acid and aqueous solutions from the leaching of urban minerals by phosphoric acid, in view of making profitable use of the rare earths present in these solutions.

Abstract: 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).

Abstract: A mesoporous organic material which makes it possible to extract, using the liquid-solid extraction technique, the uranium(VI) contained in an aqueous medium including phosphoric acid, with high efficiency and high selectivity for the iron that the medium can likewise contain. The material is likely to be obtained by cross-linking polymerisation of a monomer of formula (I) below, wherein: R1, R2 and R3 are, independently from one another, H, a C1 to C12 saturated or unsaturated, linear or branched hydrocarbon group, or a polymerisable group, with the condition that at least one of R1, R2 and R3 is a polymerisable group; R4 and R5 are, independently from one another, H or a C1 to C8 saturated or unsaturated, linear or branched hydrocarbon group; the cross-linking polymerisation being carried out in the presence of a cross-linking agent and one or more pore-forming agents.

Abstract: A new column-based purification system and approach are described for rapid separation and purification of the alpha-emitting therapeutic radioisotope 211At from dissolved cyclotron targets that provide highly reproducible product results with excellent 211At species distributions and high antibody labeling yields compared with prior art manual extraction results of the prior art that can be expected to enable enhanced production of purified 211At isotope products suitable for therapeutic medical applications such as treatment of cancer in human patients.

Abstract: A method includes supplying a reagent to a column, where the column is configured to purify an element from a sample matrix for isotopic analysis. The method also includes loading the column with the sample matrix, and supplying a second reagent to collect the element retained by the column. The method further includes loading the column with a second sample mixture, and collecting an element from the second sample mixture retained by the column. A column configured to separate an element from a sample matrix for isotopic analysis includes a resin configured to retain the element. The column also includes a first frit disposed of a first end of the column and a second frit disposed of a second end of the column. The column is configured to receive a first reagent in a first flow direction and a second reagent in a second flow direction different from the first flow direction.

Abstract: The invention discloses a measurement apparatus for measuring a volume of a desired solid component in a sample volume of a solid-liquid slurry. The sample volume of the slurry is received into a receptacle and screened to separate out the desired solid component from a remainder of the slurry, whereby the solid component is retained in the receptacle to form a bed therein and the remainder is exhausted. The height of the bed is subsequently measured by a laser being adapted to emit a laser beam into the receptacle, thereby enabling a determination of a volume and/or mass of the solid component retained in the receptacle. The invention further discloses a control system for a leaching plant utilising the measurement apparatus.

Abstract: Methods for a facile, template free and one-step synthesis of nanoporous carbons by using a heterocyclic aromatic organic compound as a single source precursor of both carbon and nitrogen are described. The heterocyclic aromatic organic compound contains nitrogen in pyrrolic and/or pyridinic positions and is chemically activated with NaOH, KOH or ZnCl2 at high temperatures in a solid state mixture as a synthesis protocol to promote fine micropores during carbonization. Nanoporous carbons synthesized by these methods that have superior gas sorption/storage and energy storage properties are also described. The nanoporous carbons are useful as carbon sequestration agents and supercapacitors.

Abstract: The present invention provides a method for easy and efficient recovery of high purity scandium from nickel oxide ore, the method comprising: an adsorption step for passing a scandium-containing solution through an ion exchange resin to adsorb scandium on the ion exchange resin; an elution step for eluting scandium from the ion exchange resin to obtain a post-elution solution; an impurity extraction step in which after the elution step, the scandium-containing solution is subjected to a first solvent extraction using an amine-based impurity extractant and is separated into a first aqueous phase containing scandium and into a first organic phase containing impurities; and a scandium extraction step in which the first aqueous phase is subjected to a second solvent extraction using an amide derivative-containing scandium extractant to obtain a second organic phase containing scandium.

Abstract: Disclosed herein are methods, techniques, and processes for enhancing the purity of a mixed rare earth solution. In one embodiment the rare earth mixture may include Lanthanum, Cerium, Praseodymium, Neodymium, Promethium, Samarium, Europium, Gadolinium, Terbium, Dysprosium, Holmium, Erbium, Thulium, Ytterbium, Lutetium, Scandium, and/or Yttrium. In one embodiment, the resin is a chelating resin that interacts poorly with one or more rare earth elements. In one embodiment a rare earth is selectively excluded for example, Lanthanum (sometimes considered a transition metal), Cerium, Praseodymium, Neodymium, Promethium, Samarium, Europium, Gadolinium, Terbium, Dysprosium, Holmium, Erbium, Thulium, Ytterbium, Lutetium, Scandium, and/or Yttrium. In one embodiment, yttrium is selectively excluded from the column.

Abstract: Hybrid media formed by combining a metal precursor solution with particulate media to yield a mixture, decanting the mixture to yield a decanted mixture, heating the decanted mixture in via microwave radiation to yield hybrid media, rinsing the hybrid media with water, soaking the rinsed hybrid media in a salt solution, and rinsing the soaked hybrid media with water. The hybrid media includes a metal dioxide derived from the metal precursor, such as TiO2 derived from TiOSO4.

Abstract: The invention relates to a method for preparing a fuel based on oxide, carbide, and/or oxycarbide comprising uranium and at least one actinide and/or lanthanide component, comprising the following steps: a step for preparing a load solution consisting in a nitric solution comprising said actinide and/or lanthanide in the form of actinide and/or lanthanide nitrates and uranium as a hydroxylated uranyl nitrate complex; a step for passing said solution over a cation exchange resin comprising carboxylic groups, with which the actinide and/or the lanthanide in cationic form and the uranium as uranyl remain bound to the resin; a heat treatment step of said resin so as to obtain said fuel.

Abstract: A solid particle for washing and the washing method using the same are provided. The solid particle is a polymer solid particle, wherein open pores are distributed on the solid particle surface. The washing method using the solid particle comprises steps of separating the articles to be washed with the solid particles, rinsing the articles to be washed and drying the articles to be washed.

Abstract: Disclosed are methods used to remove HF from a fluorocarbon containing stream, thereby forming a final aqueous HF solution having both a high HF concentration and low dissolved organic content.

Abstract: According to the present invention, there is provided a method of determining a concentration of uranium including: a) a primary measuring step of measuring luminescence intensity or luminescence attenuation of uranium (VI) of an oxidant added sample obtained by adding an oxidant composition to a detection target sample; b) a secondary measuring step of adding different volumes of standard solution containing uranium (VI) having a predetermined concentration to a plurality of oxidant added samples, respectively, and then measuring luminescence intensity or luminescence attenuation of uranium (VI) contained in each standard solution added sample; and c) a calculating step of calculating a concentration of uranium (VI) contained in the detection target sample by a standard addition method based on the primary and secondary measurements. With the method for determining a concentration of uranium according to the present invention, the concentration of uranium may be further rapidly and accurately analyzed.

Abstract: Methods of purifying acidic metal solutions by removing at least a portion of alpha-particle emitting materials are provided. The purified metal solutions are useful in a variety of applications requiring low levels of alpha-particle emission.

Abstract: In a preferred embodiment, a process for extracting uranium from wet-process phosphoric acid (WPA), comprises separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. The loaded uranium solution stream is then contacted by with an ion exchange resin. Uranium species bound to the ion exchange resin are eluted by contacting the resin with a solution comprising anions to produce a loaded uranium eluant stream. The loaded uranium eluant stream is treated to provide a uranium containing product.

Abstract: A functionalized mesoporous carbon composition comprising a mesoporous carbon scaffold having mesopores in which polyvinyl polymer grafts are covalently attached, wherein said mesopores have a size of at least 2 nm and up to 50 nm. Also described is a method for producing the functionalized mesoporous composition, wherein a reaction medium comprising a precursor mesoporous carbon, vinyl monomer, initiator, and solvent is subjected to sonication of sufficient power to result in grafting and polymerization of the vinyl monomer into mesopores of the precursor mesoporous carbon. Also described are methods for using the functionalized mesoporous carbon, particularly in extracting metal ions from metal-containing solutions.

Abstract: A process for the extraction of uranium compounds from wet-process phosphoric acid includes lowering the iron concentration of the wet-process phosphoric acid and reducing the valency of any remaining ferric iron in the wet-process phosphoric acid to ferrous iron, and then extracting uranium compounds from the wet-process phosphoric acid. The process can include separating a side stream from a feed stream of wet-process phosphoric acid, wherein the side stream has a greater concentration of the uranium compounds than the feed stream by filtration. Extracting uranium compounds from the wet-process phosphoric acid can be by ion exchange process or by solvent extraction.

Abstract: This invention relates to the integration of ammonium carbonate leach processes with established acid and alkaline uranium leach processes as multifunctional industrial processes for the extraction, high degree purification and conversion of processed or semi-processed uranium as U3O8, UO2, or most tetra or hexa-valent forms of uranium, and where applicable, for the recovery of uranium from uranium ores, using advanced multiple stage membrane based technologies for the separation and concentration of uranium in solution from heavy metals and lighter elements that may be present in the solution, and the selective leach and precipitation properties of an ammonium carbonate leach.

Abstract: The invention discloses a method for recovering uranium from an acidic leach solution or leach pulp in salt water using an amino-phosphorus resin, wherein the liquid phase of the leach solution or leach pulp contains greater than 3 g/L chloride ion in solution. The resin may comprise a functional group comprising an amino phosphonic group, an amino-phosphinic group, an amino phosphoric functional group and/or a combination thereof. According to the invention the leach solution or leach pulp may be generated by in-situ leaching, vat leaching, heap leaching and/or agitated leaching at ambient, elevated temperature and/or elevated pressure conditions in saline or hyper-saline water.

Abstract: Extraction method for recovering metals. Phosphoric acid is contacted with an extractant suspension of solid particulate material comprising a para- or ferromagnetic material core surrounded by an outer shell of a chelating polymer whereby a metal is the solution is adsorbed on the chelating polymer, thereby removing it from the phosphoric acid solution. The metal-containing solid particulate material is magnetically separated from the solution and the metal is stripped from the solid particulate material for reuse.

Abstract: The present application relates to novel monodisperse, gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is a radical —(CH2)q—COOR3, R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2, q is an integer from 1 to 5 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.

Abstract: The present application relates to novel gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is —CH2—S—CH2COOR3 or —CH2—S—C1-C4-alkyl or —CH2—S—CH2CH(NH2)COOR3 or —CH2—S—CH2—CH(OH)—CH2(OH) or or derivatives thereof or —C?S(NH2), R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.

Abstract: The present invention is directed to a new more environmentally friendly method for the recovery of uranium from pregnant liquor solutions that comprise high concentration of sulfate by using an amino phosphonic functionalized resin.

Abstract: A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.

Abstract: Disclosed herein is a uranium ion exchange adsorption method using ultrasound. The method includes placing a slurry obtained by mixing uranium ions, sulfuric acid and an ion exchange resin into a reaction bath, and stirring the slurry in the reaction bath while simultaneously applying ultrasound to the reaction bath to allow the uranium ions to be adsorbed to the ion exchange resin through ion exchange adsorption. The method has an improved ion exchange adsorption rate of the uranium ions.

Abstract: In a preferred embodiment, a process for extracting uranium from wet-process phosphoric acid (WPA), comprises separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. The loaded uranium solution stream is then contacted by with an ion exchange resin. Uranium species bound to the ion exchange resin are eluted by contacting the resin with a solution comprising anions to produce a loaded uranium eluant stream. The loaded uranium eluant stream is treated to provide a uranium containing product.

Abstract: This invention relates to the integration of ammonium carbonate leach processes with established acid and alkaline uranium leach processes as multifunctional industrial processes for the extraction, high degree purification and conversion of processed or semi-processed uranium as U3O8, UO2, or most tetra or hexa-valent forms of uranium, and where applicable, for the recovery of uranium from uranium ores, using advanced multiple stage membrane based technologies for the separation and concentration of uranium in solution from heavy metals and lighter elements that may be present in the solution, and the selective leach and precipitation properties of an ammonium carbonate leach.

Abstract: Interlayer insulating films 5,7 (insulating films) provided in a memory capacitor cell 8 are formed between a gate electrode 3 and a counter electrode 8C formed on a silicon wafer 1. The interlayer insulating films 5,7 comprise a borazine-based resin, having a specific dielectric constant of no greater than 2.6, a Young's modulus of 5 GPa or greater and a leak current of no greater than 1×10?8 A/cm2.

Abstract: A process for the extraction of uranium compounds from wet-process phosphoric acid includes lowering the iron concentration of the wet-process phosphoric acid and reducing the valency of any remaining ferric iron in the wet-process phosphoric acid to ferrous iron, and then extracting uranium compounds from the wet-process phosphoric acid. The process can include separating a side stream from a feed stream of wet-process phosphoric acid, wherein the side stream has a greater concentration of the uranium compounds than the feed stream by filtration. Extracting uranium compounds from the wet-process phosphoric acid can be by ion exchange process or by solvent extraction.

Abstract: The oxine ligands 5-chloro-8-hydroxyquiniline and 5-sulfoxyl-8-hydroxyquinoline are covalently bound, using, for example, the Mannich reaction, to a silica gel polyamine composite made from a silanized amorphous silica xerogel and polyallylamine. The resulting modified composites, termed CB-1 (X?Cl) and SB-1 (X?SO3H), respectively, show a clear selectivity for trivalent over divalent ions and selectivity for gallium over aluminum. The compounds of the invention can be applied for the sequestration of metals, such as heavy metals, from contaminated mine tailing leachates.

Abstract: The invention covers the combination of utilizing the selectivity of an adsorbent to remove species from a liquid containing mixtures of ions and then subjecting the loaded resin to a chromatographic displacement utilizing the most selectively adsorbed species to displace the undesired co-adsorbing impurities. The technique can be used even when the most selectively adsorbed species is present as a minor constituent in the feed solution.

Abstract: The present application is directed to a method for the purification of Radium, in particular 226Ra, for target preparation for an essentially pure 225Ac production from available radioactive sources, using an extraction chromatography in order to separate chemically similar elements such as Ba, Sr, and Pb from the desired Ra; wherein said extraction chromatography has an extractant system on the basis of a crown ether. The invention is further related to a method for recycling of 226Ra, for target preparation for 225Ac production from radium sources irradiated with accelerated protons (p,2n), after separation of the produced 225AC. In this method a combination of the above extraction chromatography and a cation exchange chromatography is used. The obtained 226Ra is essentially free of the following chemical contaminants consisting of Ag, Al, As, Be, Bi, Ca, Cd, Co, Cr, Cu, Fe, Ga, K, Li, Mg, Mn, Na, Ni, Pb, Sr, V, Zn, and Ba.

Abstract: The invention relates to a method for the removal of uranium(VI) species from waters by means of weakly basic, polyacrylic-based anion exchangers, said uranium(VI) species being present in the form of uranyl complexes as dissolved uranyl.

Abstract: The present invention relates to a method for the volumetric decontamination of radioactive metals. The method includes the step of precipitating out radioactive gamma and beta emitting nucleotides and then recovering non-radioactive metal compounds.

Abstract: The present application relates to novel gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is —CH2—S—CH2COOR3 or —CH2—S—C1-C4-alkyl or —CH2—S—CH2CH(NH2)COOR3 or —CH2—S—CH2—CH(OH)—CH2(OH) or or derivatives thereof or —C?S(NH2), R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.

Abstract: An extraction agent for the separation of trivalent actinides from lanthanides in an acidic media and a method for forming same are described, and wherein the methodology produces a stable regiospecific and/or stereospecific dithiophosphinic acid that can operate in an acidic media having a pH of less than about 7.

Abstract: A chemical element to be very efficiently separated from uranium starting from an acid aqueous phase, in an extraction cycle for the uranium, when this chemical element is present in said phase at a concentration less than that of the uranium, or even as a trace element, and when it is moreover less extractable by the extractant used in this extraction cycle than is the uranium. The chemical element can notably be neptunium(IV) or thorium 228.

Abstract: The present invention relates to a process for the recovery of uranium in high silica environments comprising the use of a strong base macroreticular ion exchange resin.

Abstract: A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.

Abstract: A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support.

Abstract: The present invention relates to the use of monodisperse, macroporous anion exchangers of type I or type II in hydrometallurgical processes for winning metals of value.

Abstract: A novel class of dendritic macromolecules is provided having a core, a hyperbranched structure, and a plurality of units satisfying the formula —NR2(C?O)R1, in which R1 is not a continuation of the hyperbranched structure. Methods of preparing these dendritic macromolecules are also provided, as well as methods of using dendritic macromolecules, including those described above, in separation processes or as part of in situ leach mining processes. A class of facilities for in situ leach mining is also provided.

Abstract: A method for separation of actinide elements comprising feeding a solution containing actinide elements such as americium, curium, californium and the like, into a resin column in which a weakly basic primary, secondary or tertiary anion exchange resin obtained by resinifying pyridine, imidazole or alkylamine has been packed, and then feeding an eluent of a mixed solution of nitric acid and alkyl alcohol such as methanol, ethanol, propanol and the like into the resin column to chromatographically separate the actinide elements from each other. This method makes it possible to efficiently separate the actinide elements from each other by a unit operation at ordinary temperature and ordinary pressure while avoiding oxidation operation, and hence makes it possible to avoid generation of secondary wastes and operations difficult in terms of engineering, such as precipitation.

Abstract: A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.

Abstract: A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support.

Abstract: A surface contaminated by a radioactive isotope is cleaned by applying to it a solution that contains an ion-specific resin that is weakly bonded to an ion and a weak anion solution including a carrier, water, and an ion that frees the radioactive isotope from the contaminated surface. The radioactive isotope bonds with the ion-specific resin, replacing the ion weakly bonded to said ion-specific resin. In a preferred embodiment, the ion-specific resin is made in the counterion form of citrate, the ion that is weakly bonded to the ion-specific resin is citrate, the carrier is glycerin, the water is de-ionized or distilled, and the ion that frees the radioactive isotope from the contaminated surface is salicylate.

Abstract: A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter interferents, while the desired daughter actinium ions and radium ions elute. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine.

Abstract: This invention relates to a method and an apparatus for preparing Bi-213 to be integrated in a radioimmunocojugate for human therapeutic use. According to the invention the method comprises the sequence of steps as follows: a) an ampoule 5 containing colloid-free actinium-225, obtained from drying an actinium nitrate solution, is loaded into a container 20 provided with radiation panels 21; b) a dissolving medium is poured into the ampoule 5; c) the solution obtained in the ampoule is transferred into an ion exchange column 6; d) an elution medium is circulated through the column 6; e) the eluate containing eluted Bi-213 is pumped towards a vial 10 for quantification and quality control.

Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution.