Patent Number: 
Section: description

The present invention is more particularly described in the following examples which are intended as illustrative only, since numerous modifications and variations will be apparent to those skilled in the art. A 0.97 cm diameter by 0.02 mm thick target consisting of 10.0 mg of 99.82% enriched Zn70 as oxide compacted between pure aluminum foils was irradiated for 1 hr with 18.8 MeV protons at a current of 4.00 microamperes (xcexcA). This target yielded 8.05 xcexcCi of Cu67, 0.325 xcexcCi of Ga67 and traces of other zinc and cobalt isotopes at the end of bombardment. The irradiated aluminum containing the Zn70 target was dissolved in 20 mL of 6 M HCl. Ten mL of concentrated HCl was added to adjust the molarity to about 9 M HCl and the solution was contacted with 7 mL of anion exchange resin (AG1-X8). The resin was then rinsed with 15 mL of 9 M HCl and the copper and gallium isotopes were stripped from the column with 60 mL of 2 M HCl. The strip solution was evaporated to dryness and dissolved in 3 mL of concentrated HCl. The 3 mL solution was then contacted with 3 mL of cation exchange resin (AG50-WX8) and the resin washed with 2 mL of concentrated HCl. The resin was then washed with 5 mL of concentrated HCl and collected into a clean vial. Both vials of concentrated HCl were then analyzed for Cu67 content and radioimpurities. Vial 1 contained 7.81 xcexcCi of Cu67 and a trace of cobalt isotopes. Vial 2 contained 0.235 xcexcCi of Cu67 with the same trace of cobalt isotopes as in the first vial. Total yield of Cu67 was 8.05 xcexcCi Cu67 at end of bombardment. The first anion exchange resin was washed with 2xc3x9730 mL of 2 M HNO3 to recover the enriched Zn target material. Greater than 96% of the enriched Zn70 was in the first 30 mL of wash. These solutions were combined and saved for replating a new target. A 0.97 cm diameter by 0.02 mm thick target consisting of 10.7 mg of 71.6% enriched Zn70 as oxide compacted between pure aluminum foils was irradiated for 1 hr with 18.8 MeV protons at a current of 5.11 xcexcA. This target yielded 10.4 xcexcCi of Cu67, 108 xcexcCi of Ga67 and traces of other zinc and cobalt isotopes at the end of bombardment. The irradiated aluminum containing the Zn70 target was dissolved in 20 mL of 6 M HCl. Ten mL of concentrated HCl was added to adjust the molarity to about 9 M HCl and the solution was contacted with 7 mL of anion exchange resin (AG1-X8). The resin was then rinsed with 15 mL of 9 M HCI and the copper and gallium isotopes were stripped from the column with 60 mL of 2 M HCl. The strip solution was evaporated to dryness and dissolved in 3 mL of concentrated HCl. The 3 mL solution was then contacted with 3 mL of cation exchange resin (AG50-WX8) and the resin washed with 2 mL of concentrated HCl. The 5 mL of concentrated HCl was passed through a second 3 mL cation resin column and the resin washed with 3 mL of concentrated HCl. The combined 8 mL of solution was then passed through a third 3 mL cation column and the resin was then washed with 4.85 mL of concentrated HCl and collected into a clean vial. Both vials of concentrated HCl were then combined and analyzed for Cu67 content and radioimpurities. Total yield of Cu67 was 10.4 xcexcCi Cu67 in 12.85 mL. The first anion exchange resin was washed with 2xc3x9730 mL of 2 M HNO3 to recover the enriched Zn target material. Greater than 95% of the enriched Zn70 was in the first 30 mL of wash. These solutions were combined and saved for replating a new target. Although the present invention has been described with reference to specific details, it is not intended that such details should be regarded as limitations upon the scope of the invention, except as and to the extent that they are included in the accompanying claims.