Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
10916175 | Nuclear Medicine and Biology | 2005 | 7 Pages |
Abstract
86Y is an attractive PET radionuclide due to its intermediate half-life. 86Y was produced via the 86Sr(p,n)86Y nuclear reaction. Enriched SrCO3 or SrO was irradiated with 2-6 μA of beam current for <4 h on a CS-15 cyclotron. It was shown that the SrO target could withstand at least 6 μA of beam current, a significant improvement over a maximum of 2 μA on the SrCO3 target. Average yields of 4.5 mCi/μA·h were achieved with SrO, which represent 71% of the theoretical yield, compared to 2.3 mCi/μA·h with SrCO3. The radioisotopic contaminants were 86mY (220%), 87Y (0.27%), 87mY (0.43%) and 88Y (0.024%). 86Y 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 86Y was recollected on the Pt wire after a second electrolysis. The 86Y was collected from the Pt wire using 2.8 M HNO3/EtOH (3:1). After evaporation, 86Y was reconstituted in 100 μl of 0.1 M HCl. Target materials were recovered as SrCO3 and then converted to SrO by thermal decomposition at 1150°C. Specific activity of 86Y was determined to be 29±19 mCi/μg via titration of 86Y(OAc)3 with DOTA or DTPA. We have established techniques for the routine, economical production of high purity, high specific activity 86Y on a small biomedical cyclotron that are translatable to other institutions.
Related Topics
Life Sciences
Biochemistry, Genetics and Molecular Biology
Cancer Research
Authors
Jeongsoo Yoo, Lucie Tang, Todd A. Perkins, Douglas J. Rowland, Richard Laforest, Jason S. Lewis, Michael J. Welch,