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Meeting ReportMolecular Targeting Probes - Radioactive & Nonradioactive

Cyclotron production of 68Ga using a solution target

Mukesh Pandey, Huailei Jiang, John Byrne, Alan Packard and Timothy DeGrado
Journal of Nuclear Medicine May 2014, 55 (supplement 1) 434;
Mukesh Pandey
1Mayo Clinic, Rochester, MN
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Huailei Jiang
1Mayo Clinic, Rochester, MN
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John Byrne
2Brigham and Women's Hospital, Boston, MA
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Alan Packard
3Children's Hospital Boston, Boston, MA
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Timothy DeGrado
1Mayo Clinic, Rochester, MN
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Abstract

434

Objectives To develop an efficient method for the production of 68Ga with a solution target using a medium energy cyclotron.

Methods A solution target was designed and constructed with dual foils of Al (0.20 mm) and Havar (0.038 mm) separated by helium cooling to degrade the PETtrace cyclotron proton energy to ~14 MeV. The solution target insert (1.6 mL) was made of Ta and designed with enhanced heat exchange. The target was operated as a closed system. 68Zn (99.23% isotopic enrichment) was dissolved in concentrated nitric acid, evaporated to dryness, and reconstituted with dilute nitric acid to form 1.7 M 68Zn nitrate in 0.2N nitric acid as target solution. After 30 min of proton irradiation at 20 μA, the target solution was passed through a cation exchange column (AG-50W-X8, 1.3 g), which efficiently trapped both 68Zn and 68Ga. 68Zn was subsequently eluted with 30 mL of 0.5M-HBr in 80% acetone without any measurable loss of 68Ga. The AG column was rinsed with 5 mL water to remove the HBr-acetone solution. 68Ga was eluted with 7 mL of 3N HCl solution with > 96 % elution efficiency. The radionuclidic purity was determined on an HPGe detector. Additionally, a Dionex HPLC system with post-column addition of 4-(2- pyridylazo) resorcinol and UV-detection was employed to analyze for non-radioactive metal contaminants.

Results The product yield was 1.98-2.10 GBq (53.4-56.8 mCi) decay-corrected at EOB with processing time of ~30 min. The radionuclidic purity of 68Ga was found to be >99.9%, with the predominant contaminant being 67Ga. The HPLC analysis showed Fe, Cu and Zn concentrations < 3 μg / mL. The production yield of 68Ga can be further increased by increasing 68Zn concentration in the target solution and extending irradiation time.

Conclusions A simple and efficient method of 68Ga production was developed using a medium energy cyclotron and a solution target. The developed methodology offers a cost effective alternative route to 68Ga in comparison with 68Ge-based 68Ga generators.

Research Support This work was supported by DOE (DE-SC0008947).

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Journal of Nuclear Medicine
Vol. 55, Issue supplement 1
May 2014
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Cyclotron production of 68Ga using a solution target
Mukesh Pandey, Huailei Jiang, John Byrne, Alan Packard, Timothy DeGrado
Journal of Nuclear Medicine May 2014, 55 (supplement 1) 434;

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Cyclotron production of 68Ga using a solution target
Mukesh Pandey, Huailei Jiang, John Byrne, Alan Packard, Timothy DeGrado
Journal of Nuclear Medicine May 2014, 55 (supplement 1) 434;
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