In this work, a purification method for the 68Ge/68Ga generator eluate and a method to produce 68Ga-DOTATOC suitable for clinical use were evaluated. The generator eluate was purified and concentrated on a cation-exchange cartridge in HCl/acetone media. The efficacy of this procedure in eliminating metal impurities from the 68Ga solution was investigated by ICP-MS. The radiotracer quality was evaluated by radio-TLC, GC and γ-ray spectrometry.
68Ga-DOTATOC preparations (n=33) were carried out with a mean synthesis yield of 59.3±2.8 % (not corrected for decay) and a batch activity ranging from 555 to 296 MBq. The radiochemical and radionuclidic purity were >98 % and 99.9999 % , respectively. With this purification process, >95 % of the Fe(III), Zn(II) and Mn(II) were eliminated from the solution.
68Ga-DOTATOC produced with this method can be efficiently used in nuclear medicine departments for PET evaluations.