Patent Number: 050193236
Section: claims

1. A method of producing Iodine-124, said method comprising: placing a target means comprising copper in a nickel plating solution and electroplating said target means with nickel;  placing the resulting target means in an isotopically enriched Tellurium-124 dioxide plating solution and electroplating said target means with Tellurium-124;  placing the resulting target means in line with a deuteron beam of a cyclotron, thereby irradiating the Tellurium-124 and creating Iodine-124 by the.sup.124 Te(d,2n).sup.124 I reaction; and  separating the Iodine-124 from the target means.  the target means is a copper metal plate which is first milled and uniformly lapped, said copper metal plate being sanded, washed with distilled water, and dried prior to electroplating.  Tellurium-124 electroplating is accomplished by means of a solution of isotopically enriched Tellurium-124 dioxide dissolved in a solution of potassium hydroxide and by means of a platinum electrode.  the target thickness is between 10 and 14 milligrams per square centimeter.  the Iodine-124 is used as a radioactive standard for nuclear detection calibration.  placing a target means comprising copper in a nickel plating solution and electroplating said target means with nickel;  placing the resulting target means in a Tellurium-124 plating solution and electroplating said target means with Tellurium-124;  placing the resulting target means in line with the particle beams of a cyclotron, thereby irradiating the Tellurium-124 and creating Iodine-124;  separating the Iodine-124 from the target means; and  combining the Iodine-124 with meta-iodobenzylguanidine.  the Iodine-124 is combined with the meta-iodobenzylguanidine in a method comprising the mixing of meta-iodobenzylguanidine sulphate with copper nitrate in a borosilicate serum vial, adjusting the pH to about 5, heating the solution to 150 degrees centigrade, cooling, adding a sodium biphosphate buffer solution, and passing the filtrate through an anion-exchange resin.  creating a target matrix by electroplating Tellurium-124 onto a nickel surface of a water cooled copper plate, whereby the resulting Tellurium-124 concentration is at least 0.1 milligrams per square centimeter,  bombarding the electroplated tellurium for about four hours with a 50 microampere beam current comprising deuteron particles having a particle energy of at least 6.5 MeV, thereby producing an Iodine-124 product,  allowing said iodine product to decay for about 40 hours, and separating Iodine-124 from the target matrix.  the Tellurium-124 concentration of the target matrix is about 10 to 14 milligrams per square centimeter.  the resulting Iodine-124 is incorporated into a substance selected from the group including the following: a steroidal group, an aryl group, a substituted aryl group, a vinyl group, an aryl group capable of coupling with antibodies, an aromatic amine, an aromatic isocyanate, benzoic acid, a substituted benzoic group, a vinylestradial group, monoclonal antibodies, polyclonal antibodies, steroids, cholesterol derivatives, estrogen derivatives, hormones, and proteins.  irradiation is conducted in the range of 25 to 80 microamperes deuteron beam current with irradiation doses ranging from 100 to 500 microampere hours.  disposing on a target means a substantial amount of Tellurium-124,  irradiating said Tellurium-124 and transforming a substantial amount of said Tellurium-124 into Iodine-124 by the .sup.124 Te(d,2n).sup.124 I reaction,  chemically removing said Iodine-124 from said target means to produce a solution having radioisotopes of iodine which are primarily Iodine-124,  removing from said solution a substantial portion of deleterious salts, whereby autoradiolytic decomposition of said Iodine-124 is substantially reduced.  preparing an ion exchange column and passing said solution through said column, and  heating said solution to reduce the volume so that its final concentration is about 15 to 120 mCi per 1.0 ml or greater specific activity.  said Iodine-124 is separated from trace Tellurium, and  said solution is subsequently purified by removing salts from said solution by preparing an ion exchange column and passing said solution through said column, and  heating said solution to reduce its volume so that its concentration is about 15 to 120 mCi per 1.0 ml. or greater specific activity. 2. The method of producing Iodine-124 of claim 1 wherein: 3. The method of producing Iodine-124 of claim 2 wherein: 4. The method of producing Iodine-124 of claim 3 wherein: 5. The method of producing Iodine-124 of claim 1 wherein the irradiated target is placed in a solution of sodium hydroxide solution containing hydrogen peroxide and water, subsequently, the solution is transferred to a vessel containing aluminum powder, thereafter the solution so purged with air, then carbon dioxide gas, particles in the solution are then filtered out and passed through a cation-exchange column. 6. The method of making Iodine-124 in claim 1 whereby: 7. A method of synthesizing Iodine-124 labeled meta-iodobenzylguanidine, said method comprising: 8. The method of claim 7 wherein 9. A method of synthesizing Iodine-124 to a purity of about 99.5%, said method comprising: 10. The method of synthesizing Iodine-124 of claim 9 whereby: 11. The method of synthesizing Iodine-124 of claim 10 whereby: 12. The method of making Iodine-124 of claim 9 wherein: 13. A method of making and purifying an Iodine-124 solution comprising the steps of: 14. A method of making and purifying an Iodine-124 solution in accordance with claim 13 wherein said step of removing salts from said solution includes: 15. A method of making and purifying an Iodine-124 solution in accordance with claim 13 wherein: