Electrochemical separation and purification of yttrium-86
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G. Reischl
Summary
For quantitative determination of in vivo dosimetry of 90Y-labeled radiotherapeuticals by means of PET, the positron emitting analogue yttrium-86 was produced at a low energy (“medical”) cyclotron via the known 86Sr(p, n)86Y reaction. Using 200 mg of 86SrCO3 (enrichment 95.6%) and protons of 15.1 MeV energy, average yields of 86Y of 48 ± 8 MBq/µA h were produced. After dissolution of 86SrCO3 in 3 ml of 0.6 N HNO3, 86Y was deposited in a simple and highly efficient electrochemical two-step procedure onto a platinum cathode at 450 mA (= 20 mA/cm2). The isotope was finally removed from the electrode by 100–300 µl of 0.5–1.0 N HCl or 0.3–0.6 N HNO3 resulting in an overall recovery of 88 ± 6% (corrected for decay). Up to 1 GBq of 86Y with high radionuclidic and radiochemical purity were obtained after a 2.5 h irradiation and a radiochemical separation time of 2 h. An ICP/AES analysis of the separated fraction showed a very small amount of strontium (< 0.1 ppm). The chemical purity of 86Y, essential for efficient labeling, was successfully demonstrated by means of complex formation with DOTA and a DOTA-conjugated peptide, exhibiting labeling yields higher than 98%.
© Oldenbourg Wissenschaftsverlag, München
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Articles in the same Issue
- Charge and mass distribution in 7Li induced fission of 232Th
- Direct evidence for enhanced inner-sphere chloro complexation of Eu(III) and Cm(III) in anion exchange resin phase studied by time-resolved laser-induced fluorescence spectroscopy
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- Electrochemical separation and purification of yttrium-86
- Radiobromination of closo-dodecaborate anion. Aspects of labelling chemistry in aqueous solution using Chloramine-T
- Metal-ion speciation in blood plasma incorporating the water-soluble polymer, polyethyleneimine functionalised with methylenephosphonate groups, in therapeutic radiopharmaceuticals
