Ut-battelle, Inc.

Martin Marietta Energy Systems, Inc.

Lockheed Martin Energy Systems, Inc.

Lockheed Martin Energy Research Coirporation

Saed Mirzadeh

Furn F Knapp, Jr

Arnold L Beets

Miting Du

Alvin P Callahan

Edward C Lisic

Michael Z Hu

David W DePaoli

Emory D Collins

Rose Ann Boll

John W Clavier

Marc Alan Garland

Stefan Guhlke

Applicant's invention is a radionuclide generator resin material for radiochemical separation of daughter radionuclides, particularlyBi, from a solution of parental radionuclides, the resin material capable of providing clinical quantities ofBi of at least 20-mCi, wherein the resin material comprises a silica-based structure having at least one bifunctional ligand covalently attached to the surface of the silica-based structure. The bifunctional ligand comprises a chemical group having desirable surface functionality to enable the covalent attachment of the bifunctional ligand thereon the surface of the structure and the bifunctional ligand further comprises a second chemical group capable of binding and holding the parental radionuclides on the resin material while allowing the daughter radionuclides to elute off the resin material. The bifunctional ligand has a carbon chain with a limited number of carbons to maintain radiation stability of the resin material.

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A method for producingTh includes the steps of providingRa as a target material, and bombarding the target material with alpha particles, helium-3, or neutrons to formTh. When neutrons are used, the neutrons preferably include an epithermal neutron flux of at least 1&#xd7;10n s&#xb7;cm.Ra can also be bombarded with thermal and/or energetic neutrons to result in a neutron capture reaction to formTh. UsingTh as a target material,Th can be formed using neutron, gamma ray, proton or deuteron bombardment.

Production of thorium-229 using helium nuclei

A method of producing and purifying promethium-147 including the steps of: irradiating a target material including neodymium-146 with neutrons to produce promethium-147 within the irradiated target material; dissolving the irradiated target material to form an acidic solution; loading the acidic solution onto a chromatographic separation apparatus containing HDEHP; and eluting the apparatus to chromatographically separate the promethium-147 from the neodymium-146.

Chromatographic extraction with di(2-ethylhexyl)orthophosphoric acid for production and purification of promethium-147

A new composition of matter includes Pt characterized by a specific activity of at least 30 mCi/mg Pt, generally made by method that includes the steps of: exposing Ir to a flux of neutrons sufficient to convert a portion of the Ir to Pt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce Pt.

High specific activity platinum-195m

A method of preparing high-specific-activity Pt includes the steps of: exposing Ir to a flux of neutrons sufficient to convert a portion of the Ir to Pt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce Pt.

Method of preparing high specific activity platinum-195m

A method of separating lutetium from a solution containing Lu and Yb, particularly reactor-produced Lu and Yb, includes the steps of: providing a chromatographic separation apparatus containing LN resin; loading the apparatus with a solution containing Lu and Yb; and eluting the apparatus to chromatographically separate the Lu and the Yb in order to produce high-specific-activity Yb.

Method for preparing high specific activity 177Lu

A .sup.99 Mo/.sup.99m Tc generator system includes a sorbent column loaded with a composition containing .sup.99 Mo. The sorbent column has an effluent end in fluid communication with an anion-exchange column for concentrating .sup.99m Tc eluted from the sorbent column. A method of preparing a concentrated solution of .sup.99m Tc includes the general steps of: a. providing a sorbent column loaded with a composition containing .sup.99 Mo, the sorbent column having an effluent end in fluid communication with an anion-exchange column; b. eluting the sorbent column with a salt solution to elute .sup.99m Tc from the sorbent and to trap and concentrate the eluted .sup.99m Tc on the ion-exchange column; and c. eluting the concentrated .sup.99m Tc from the ion-exchange column with a solution comprising a reductive complexing agent.

Technetium-99m generator system

A method of preparing a concentrated solution of a carrier-free radioisotope which includes the steps of:

Concentration of perrhenate and pertechnetate solutions

A generator system for providing a carrier-free radioisotope in the form of an acid comprises a chromatography column in tandem fluid connection with an ion exchange column, the chromatography column containing a charge of a radioactive parent isotope. The chromatography column, charged with a parent isotope, is eluted with an alkali metal salt solution to generate the radioisotope in the form of an intermediate solution, which is passed through the ion-exchange column to convert the radioisotope to a carrier-free acid form.

Growing community of inventors

Knoxville, TN, United States of America

Saed Mirzadeh