Influential Factors in the Preparation of 68Ga-DOTATATE

A comparison of routine [68Ga]Ga-PSMA-11 preparation using Locametz and Illuccix kits

BACKGROUND

Approval of Locametz and Illuccix kits for the manufacture of [68Ga]Ga-PSMA-11 (gallium Ga68 gozetotide), a PET imaging agent for prostate cancer, as well as the corresponding therapeutic ([177Lu]Lu-PSMA-617 Pluvicto), has led to a rapid increase in demand for [68Ga]Ga-PSMA-11 PET imaging. Radiopharmaceutical manufacturers, using 68Ge/68Ga generators, may decide to adopt Locametz and/or Illuccix kits, which requires a comparison to select the most suitable kit for day-to-day use. The objective of this article is to compare both kits and provide guidance for selecting one for routine use, as well as evaluate labeling consistency of both kits during routine production. Additionally, we report our experience during 1.5 years of daily [68Ga]Ga-PSMA-11 production at our facility using both kits.

RESULTS

Locametz (n = 181) and Illuccix (n = 256) kits were prepared using non-silicone coated and silicone-coated needles with 68Ga activities ranging from 0.53 to 3.16 GBq, with a failure rate of 1 in 128 runs for both kits. With Locametz, a 3.7 GBq generator and 10-min incubation at room temperature gave doses that passed quality control (QC) testing. Use of non-silicone coated needles in the process led to solution discoloration, and QC failure. Additionally, lack of vial inversion led to inconsistent labeling, which improved with subsequent vial agitation. For Illuccix, addition of the acetate buffer to the precursor vial prior to adding the [68Ga]GaCl3 simplifies the workflow. The maximum tolerated activity was 1.85 GBq. Lack of vial inversion led to failures, which were rectified by agitating the vial to properly incorporate the acetate solution with the generator eluate.

CONCLUSIONS

Both kits benefited from using a syringe pump to elute the 68Ge/68Ga generator, vial agitation, and longer length/smaller bore silicone coated needles. Both kits have similar workflows, comparable QC outcomes, and result in equivalent clinical images. Thus, the decision between kits will ultimately be determined by production preferences. Since radiopharmacies have an established "kit-based" workflow, Locametz kits with higher allowed activities and longer shelf-life may offer benefits. Conversely, more traditional PET manufacturing facilities might benefit from using Illuccix kits due to compatibility with cyclotron-produced [68Ga]GaCl3 allowing for kit batching. Ultimately, the commercial availability of 2 approved kits for production of [68Ga]Ga-PSMA-11 PET has facilitated ready access to this important new imaging agent.

Production and purification of 43Sc and 47Sc from enriched [46Ti]TiO2 and [50Ti]TiO2 targets

The radioscandium isotopes, 43Sc and 47Sc, compose a promising elementally matched theranostic pair that can be used for the development of imaging and therapeutic radiopharmaceuticals with identical structures. This study aimed to investigate the production of high radionuclidic purity 43Sc from enriched [46Ti]TiO2 targets and 47Sc from enriched [50Ti]TiO2 targets and establish a target recycling technique. Enriched [46Ti]TiO2 targets were irradiated with 18 MeV protons, and enriched [50Ti]TiO2 targets were bombarded with 24 MeV protons. 43Sc and 47Sc were purified using ion chromatography attaining recovery yields of 91.7 ± 7.4% and 89.9 ± 3.9%, respectively. The average radionuclidic purity for 43Sc was 98.8 ± 0.3% and for 47Sc 91.5 ± 0.6%, while the average recovery of enriched titanium target material was 96 ± 4.0%. The highest apparent molar activity for [43Sc]Sc-DOTA was 23.2 GBq/µmol and 3.39 GBq/µmol for [47Sc]Sc-DOTA. This work demonstrates the feasibility of using enriched recycled [46Ti]TiO2 and [50Ti]TiO2 targets to produce high purity 43Sc and 47Sc as an elementally matched theranostic isotope pair.