Studies of adsorber materials for preparing 68Ge/68Ga generators

The 68Ga is a promising radionuclide for nuclear medicine, decaying by positron emission with an abundance of 89%, with physical half-life of 68 minutes, which is compatible with the pharmacokinetics of many biomolecules and low molecular weight substrates. Another important feature is its availability through a generator system, where the parent radionuclide, 68Ge (t1/2 = 270.95 days) is adsorbed on a column and the daughter, 68Ga, is eluted in an ionic form 68Ga3+. The development of 68Ge/68Ga generators began in the 60s, but its clinical use began to be acceptable and relevant only recently. The method of separation of 68Ge and 68Ga most used is the ion-exchange chromatographic system, due to its practical operation, but other generator systems have been proposed, such as solvent extraction and evaporation technique. Currently, 68Ge/68Ga generators are commercially available using inorganic matrices columns prepared with TiO2 or SnO2 as well using organic resin. The efficiency of 68Ga elution ranges from 70% to 80%, decreasing over time. The 68Ge breakthrough varies from 10-2 to10-3 % or lower in a fresh generator, but there is an increase in the levels of contamination after long periods of use. Even with all the technological advances in the development of 68Ge/68Ga generators in the past decades, the 68Ga eluted from commercial generators is not suitable for direct use in humans and some improvements in the systems need to be made to reduce the 68Ge breakthrough and chemical impurities levels. The main objective of this work was to develop a 68Ge/68Ga generator system is which 68Ga could be eluted with quality required for clinical use. The chemical behavior of Ge and Ga was evaluated on various inorganic adsorbents materials. Two types of 68Ge/68Ga generator systems were developed using TiO2 as adsorbent material: elution system with manual pressure and vacuum controlled. The efficiencies of the generators were similar to those found in commercial generators, as well as the impurity levels in the eluate. A new method for radionuclidic control was developed and showed good results for the determination of 68Ge breakthrough in 68Ga eluate. It was proposed a prototype 68Ga generator capable of providing the quality needed for use in medical applications. (author)