Preparation of high specific activity 86Y using a small biomedical cyclotron

(86)Y is an attractive PET radionuclide due to its intermediate half-life. (86)Y was produced via the (86)Sr(p,n) 86Y nuclear reaction. Enriched SrCO(3) or SrO was irradiated with 2-6 mu A of beam current for <4 It on a CS-I 5 cyclotron. It was shown that the SrO target could withstand at least 6 mu A of beam current, a significant improvement over a maximum of 2 mu A on the SrCO(3) target. Average yields of 4.5 mCi/mu A (.) It were achieved with SrO, which represent 71% of the theoretical yield, compared to 2.3 mCi/mu A (.) It with SrCO(3). The radioisotopic contaminants were (86m)Y (220%), (87)Y (0.27%), (87m)Y (0.43%) and (88)Y (0.024%). (86)Y was isolated in an electrochemical cell consisting of three Pt electrodes. The solution was electrolyzed at 2000 mA (40 min) using two Pt plate electrodes. A second electrolysis (230 mA for 20 min) was performed using one Pt plate and a Pt wire. On average, 97.1% of the (86)Y was recollected on the Pt wire after a second electrolysis. The (86)Y was collected from the Pt wire using 2.8 M HNO(3)/EtOH (3: 1). After evaporation, (86)Y was reconstituted in 100 mu l of 0.1 M HCl Target materials were recovered as SrCO(3) and then converted to SrO by thermal decomposition at 1150 degrees C. Specific activity of (86)Y was determined to be 29 +/- 19 mCi/mu g via titration of (86)Y(OAc)(3) With DOTA or DTPA. We have established techniques for the routine, economical production of high purity, high specific activity (86)Y on a small biomedical cyclotron that are translatable to other institutions. (c) 2005 Published by Elsevier Inc.