Arch Development Corporation

The United States of America As Represented by the United States

Pg Research Foundation, Inc.

University of Tennessee Research Foundation

Battelle Energy Alliance, LLC

Northern Illinois University

The United States of America As Represented by the Department of Energy

Eichrom Industries, Inc.

Other

Arch Develop.

Argonne National Laboratory/university of Chicago Development Corp.

E Philip Horwitz

Mark L Dietz

Andrew H Bond

Spiro D Alexandratos

Renato Chiarizia

Ralph C Gatrone

Richard E Barrans, Jr

Terry Allen Todd

Troy Joseph Tranter

David Herbert Meikrantz

John J Hines

George W Mason

Ronato Chiarizia

Robin Rogers

Richard A Bartsch

Michael J Gula

Christopher A Shelley

Andrzej W Trochimcznk

Walter H Delphin

Dale G Kalina

Michael Krumpelt

David B Dreisinger

John Young

James T Harvey

George F Vandegrift

Alice M Essling

Donald G Graczyk

Alan B Rothman

Sui Xue

David Rausch

Daniel R McAlister

Louis Kaplan

Pier R Danesi

Xue Sui

A product includes actinium-225 (Ac) and less than about 1 microgram (&#x3bc;g) of iron (Fe) per millicurie (mCi) of actinium-225. The product may have a radioisotopic purity of greater than about 99.99 atomic percent (at %) actinium-225 and daughter isotopes of actinium-225, and may be formed by a method that includes providing a radioisotope mixture solution comprising at least one of uranium-233 (U) and thorium-229 (Th), extracting the at least one of uranium-233 and thorium-229 into an organic phase, substantially continuously contacting the organic phase with an aqueous phase, substantially continuously extracting actinium-225 into the aqueous phase, and purifying the actinium-225 from the aqueous phase. In some embodiments, the product may include less than about 1 nanogram (ng) of iron per millicurie (mCi) of actinium-225, and may include less than about 1 microgram (&#x3bc;g) each of magnesium (Mg), Chromium (Cr), and manganese (Mn) per millicurie (mCi) of actinium-225.

Actinium radioisotope products of enhanced purity

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.

Process for radioisotope recovery and system for implementing same

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.

Multivalent metal ion extraction using diglycolamide-coated particles

A purification method is disclosed for a predetermined water-insoluble extractant present in a liquid phase composition that additionally contains one or more additional extractants, synthesis reaction starting materials, and reaction byproducts dissolved as solutes in an organic diluent. An ion-containing compound is admixed with the composition to form an extractant/ion complex in the organic diluent phase that has an affinity for a new phase that is greater than the affinity for the first-named phase. The predetermined extractant/ion complex is separated from the diluent by using the new phase affinity, and the extractant/ion complex is preferably although not necessarily recovered. The extractant/ion complex is separated into extractant and ion. The extractant is recovered. Exemplary extractants include polyethers, crown ethers, crown thioethers, calixarenes, polyamines, cryptands, porphyrins and the like.

Purification of 4,4'(5&#x2032;)- di-t-butylcyclohexano-18-crown-6

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.

Multicolumn selectivity inversion generator for production of high purity actinium for use in therapeutic nuclear medicine

A multicolumn selectivity inversion generator separation method has been developed in which a desired daughter radionuclide is selectively extracted from a solution of the parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter impurities, while the desired daughter elutes. 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.

Multicolumn selectivity inversion generator for production of ultrapure radionuclides

A multicolumn selectivity inversion generator has been developed in which bismuth-213 is selectively extracted from an HCl solution of the actinium-225 parent (and its radiogenic descendents) by a primary separation column containing a separation medium containing a neutral oxygenated organophosphorus extractant. After rinsing with dilute HCl, the bismuth-213 is stripped with a buffered NaCl solution. The stripped solution is passed through a cation-exchange resin guard column that retains the actinium-225 and radium-225 contaminants while the bismuth-213 elutes. This generator method minimizes the unpredictable effects of radiation damage to the support material and permits the reliable production of bismuth-213 of high chemical and radionuclidic purity.

Production of ultrapure bismuth-213 for use in therapeutic nuclear medicine

A gas-free system for separating a solution of substantially impurity-free daughter products from an associated parent load solution includes a pump, a plurality of multi-port valves, separation medium and a processor. An uncoiled conduit extends between a third port of a second multi-port valve and a first multi-port valve. A processor is operably coupled to a pump, and the plurality of multi-port valves. A method for separating a solution of substantially impurity-free daughter product from an associated parent load solution is also disclosed.

Automated radionuclide separation system and method

An extractant medium for extracting alkaline earth cations from an aqueous acidic sample solution is described as are a method and apparatus for using the same. The separation medium is free of diluent, free-flowing and particulate, and comprises a Crown ether that is a 4,4&prime;(5&prime;)&lsqb;C -C -alkylcyclohexano&rsqb;18-Crown-6 dispersed on an inert substrate material.

Alkaline earth cation extraction from acid solution

A cross-linked water-insoluble ion exchange resin comprised of polymerized monomers having a phenyl ring is disclosed. A contemplated resin contains (i) polymerized phenyl ring-containing monomers having a phosphonic acid ligand linked to the phenyl ring, (ii) about 2 to about 5 millimoles per gram (mmol/g) of phosphorus as phosphonic acid ligands, and (iii) a sufficient amount of a sulfonic acid ligand such that the ratio of mmol/g of phosphonic acid to mmol/g sulfonic acid is up to . A process for removing polyvalent metal cations from aqueous solution, and a process for removing iron(III) cations from acidic copper(II) cation-containing solutions that utilize the contemplated resin or other resins are disclosed.

Bifunctional phenyl monophosphonic/sulfonic acid ion exchange resin and process for using the same

The invention relates to a process for separating and purifying multi-curie quantities,Y of sufficient chemical and radiochemical purity suitable for use in medical applications without a series of,Sr selective extraction chromatographic columns while minimizing loss of radioactive,Sr parent and waste stream. The process includes dissolving a nitrate salt of an original,Sr stock solution in H,O creating a strontium nitrate solution; acidifying the strontium nitrate solution containing,Y with concentrated nitric acid; evaporating the strontium nitrate solution; filtering or centrifuging strontium nitrate solution to separate crystalline,Sr nitrate salt from the solution; evaporating the remaining,Y enriched supernate to dryness; dissolving the remaining,Y enriched supernate in a strong acid; passing the solution through an yttrium selective extraction chromatographic column; rinsing the yttrium selective extraction chromatographic column with strong acid; and eluting yttrium from yttrium selective extraction column with strong acid.

Method for isolating and purifying 90Y From 90strontium in multi-curie quantities

A process for converting UF,to a solid uranium compound such as UO,and CaF. The UF,vapor form is contacted with an aqueous solution of NH,OH at a pH greater than 7 to precipitate at least some solid uranium values as a solid leaving an aqueous solution containing NH,OH and NH,F and remaining uranium values. The solid uranium values are separated from the aqueous solution of NH,OH and NH,F and remaining uranium values which is then diluted with additional water precipitating more uranium values as a solid leaving trace quantities of uranium in a dilute aqueous solution. The dilute aqueous solution is contacted with an ion-exchange resin to remove substantially all the uranium values from the dilute aqueous solution. The dilute solution being contacted with Ca(OH),to precipitate CaF,leaving dilute NH,OH.

Conversion of depleted uranium hexafluoride to a solid uranium compound

A cross-linked water-insoluble ion exchange resin comprised of polymerized monomers having a phenyl ring is disclosed. A contemplated resin contains (i) polymerized phenyl ring-containing monomers having a phosphonic acid ligand linked to the phenyl ring, (ii) about 2 to about 5 millimoles per gram (mmol/g) of phosphorus as phosphonic acid ligands, and (iii) a sufficient amount of a sulfonic acid ligand such that the ratio of mmol/g of phosphonic acid to mmol/g sulfonic acid is up to 3:1. A process for removing polyvalent metal cations from aqueous solution, and a process for removing iron(III) cations from acidic copper(II) cation-containing solutions that utilize the contemplated resin or other resins are disclosed.

Growing community of inventors

Naperville, IL, United States of America

E Philip Horwitz