Production and separation of non-carrier-added 86Y from enriched 86Sr targets.

The metallic radionuclide (86)Y was produced by irradiation of enriched (86)SrCO(3) on a low-energy proton-only cyclotron. Irradiations up to 20 microA for 2h were performed with 11 MeV protons using a water-cooled target mounting with circulating chilled helium. Experimental thick target yields of 26.7 mCi/microA yielded 24 mCi of (86)Y in 2h of bombardment at 10 microA. The difference in solubility products between Y(OH)(3) and Sr(OH)(2) allows the separation of (86)Y from an alkaline strontium solution by using filter paper with an overall yield of 88 +/- 3%. The concentration of Sr in the final product was found to be on the order of 15 ppm when using 200mg of target material as determined by ICP-MS analysis. The reactivity of (86)Y was determined to be on the order of 1.5 +/- 0.8 Ci/micromol of DOTA. The enriched target material was recovered and converted to its original chemical form with an overall efficiency >90%.