Production and separation of Sc for radiopharmaceutical purposes.

BACKGROUND

The favorable decay properties of Sc and Sc for PET make them promising candidates for future applications in nuclear medicine. An advantage Sc (T = 3.89 h, Eβ = 476 keV [88%]) exhibits over Sc, however, is the absence of co-emitted high energy γ-rays. While the production and application of Sc has been comprehensively discussed, research concerning Sc is still in its infancy. This study aimed at developing two different production routes for Sc, based on proton irradiation of enriched Ti and Ca target material.

RESULTS

Sc was produced the Ti(p,α)Sc and Ca(p,n)Sc nuclear reactions, yielding activities of up to 225 MBq and 480 MBq, respectively. Sc was chemically separated from enriched metallic Ti (97.0%) and CaCO (57.9%) targets, using extraction chromatography. In both cases, ~90% of the final activity was eluted in a small volume of 700 μL, thereby, making it suitable for direct radiolabeling. The prepared products were of high radionuclidic purity, i.e. 98.2% Sc were achieved from the irradiation of Ti, whereas the product isolated from irradiated Ca consisted of 66.2% Sc and 33.3% Sc. A PET phantom study performed with Sc, both nuclear reactions, revealed slightly improved resolution over Sc. In order to assess the chemical purity of the separated Sc, radiolabeling experiments were performed with DOTANOC, attaining specific activities of 5-8 MBq/nmol, respectively, with a radiochemical yield of >96%.

CONCLUSIONS

It was determined that higher Sc activities were accessible the Ca production route, with a comparatively less complex target preparation and separation procedure. The product isolated from irradiated Ti, however, revealed purer Sc with minor radionuclidic impurities. Based on the results obtained herein, the Ca route features some advantages (such as higher yields and direct usage of the purchased target material) over the Ti path when aiming at Sc production on a routine basis.