RESUMEN
An improved chemical strategy for processing of the generator produced (68)Ga was developed based on processing of the original (68)Ge/(68)Ga generator eluate on a micro-column. Direct pre-concentration and purification of the eluted (68)Ga is performed on a cation-exchange resin in hydrochloric acid/acetone media. A supplementary step based on a second micro-column filled with a second resin allows direct re-adsorption of (68)Ga eluted from the cation exchanger. (68)Ga is finally striped from the second resin with a small volume of pure water. For this purpose a strong anion exchanger and a novel extraction chromatographic resin based on tetraalkyldiglycolamides are characterized. The strategy allows online pre-concentration and purification of (68)Ga from the original generator eluate. The supplementary column allows transferring (68)Ga with high radionuclide and chemical quality in the aqueous solution with small volume and low acidity useful for direct radiolabeling reactions.
RESUMEN
Nuclear transformation of the target material is considered as an essential parameter for the specific activity of (177)Lu produced via (176)Lu(n, gamma)(177)Lu nuclear reactions. It is shown that (176)Lu burn-up has to be taken into account to estimate the (177)Lu specific activity related to the total mass or amount of lutetium in the system.
