Abstract
New 68Ge/68Ga radionuclide generators provide the positron emitter 68Ga (T½ = 67.7 min) as an easily available and relatively inexpensive source of a PET nuclide for labeling of interesting targeting vectors. However, currently available “ionic” 68Ge/68Ga radionuclide generators are not necessarily optimized for the routine synthesis of 68Ga-labeled radiopharmaceuticals in a clinical environment. Post-processing of 68Ge/68Ga generators using cation exchange resins provides chemically and radiochemically pure 68Ga with 97±2% within less than 4 min, with 68Ge almost completely removed, and ready for online labeling. This simple, fast, and efficient technology can be extended for new applications. The options are (a) to transfer 68Ga from the cation exchange resin onto an anion exchange resin, to remove acetone, and to further purify the 68Ga, (b) to obtain 68Ga in pure non-aqueous solution via 68Ga(acac)3 as a synthon for syntheses in organic solvents, and (c) to create an option toward instantaneous determination of 68Ge breakthrough, what may be required prior to the release of 68Ga radiopharmaceutical preparations.
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Abbreviations
- TODGA:
-
N,N,N’,N’-tetra-n-octyldiglycolamide
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Rösch, F. (2013). Post-Processing via Cation Exchange Cartridges: Versatile Options. In: Baum, R., Rösch, F. (eds) Theranostics, Gallium-68, and Other Radionuclides. Recent Results in Cancer Research, vol 194. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-27994-2_3
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DOI: https://doi.org/10.1007/978-3-642-27994-2_3
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