Preparation and evaluation of SnO2-based 68Ge/68Ga generator made from 68Ge produced through (nat)Zn(α,xn) reaction

Development of a SnO2-based 44Ti/44Sc generator for medical applications

Towards application of 44Sc for diagnostic nuclear medicine, a 44Ti/44Sc generator based on an inorganic resin has been evaluated. Unlike other radionuclide generators used for medical applications, the long-term retention of the parent 44Ti is vital due to its long half life. Herein, tin dioxide (SnO2), a robust inorganic-based resin, has been synthesized and used as the stationary phase for a 44Ti/44Sc generator. The sorption behavior of 44Ti/44Sc was tested on SnO2 with varying acids, concentrations, and times. Preliminary batch study results showed >88 % 44Ti retention to the resin at lower acid concentrations (0.05 M HNO3 and 0.05 M HCl). A pilot generator was evaluated for a year, demonstrating 85.3 ± 2.8 % 44Sc elution yields and 0.71 ± 0.14 % 44Ti breakthrough in 5 M HNO3. Based on capacity studies, a 7.4 MBq (200 µCi) upscaled generator system was constructed for further evaluation of the SnO2 resin stability and the efficacy of the eluted 44Sc for radiolabeling. 44Sc could be regularly eluted from this generator in 5 M HNO3 with an overall average radiochemical yield 84.7 ± 9.5 %. Post-elution processing of the 44Sc with DGA-normal resin removed all 44Ti present and allowed for high 44Sc-DOTA labeling yields of 94.2 ± 0.5 %. Overall, SnO2 has been shown to be a viable material for a 44Ti/44Sc generator.

Production of medical isotope 68Ge based on a novel chromatography separation technique and assembling of 68Ge/68Ga generator

A double-column chromatography separation technique was involved for isolation of ⁶⁸Ge from a bombarded Ga-Ni alloy target. About 185 MBq ⁶⁸Ge obtained was used for assembling SnO₂-based ⁶⁸Ge/⁶⁸Ga generator. Approximately 70% of ⁶⁸Ga in high radioactivity concentration was eluted from generator with excellent radionuclidic, radiochemical and chemical purity. ⁶⁸Ga was quite adequate for radiolabeling with DOTATATE or PSMA-617 with a high labelling efficiency of >92%. The double-column chromatography technique possessed a potential application prospect of ⁶⁸Ge/⁶⁸Ga production, aiding the development of ⁶⁸Ga in nuclear medicine.

A simple method for preparation of pure 68 Ga-acetate precursor for formulation of radiopharmaceuticals: Physicochemical characteristics of the 68 Ga eluate of the SnO2 based-68 Ge/68 Ga column generator

Gallium-68 radioisotope is an excellent source in clinical positron emission tomography application due to its ease of availability from germanium-68 (⁶⁸ Ge)/gallium-68 (⁶⁸ Ga) generator having a shelf life of 1 year. In this paper, a modified method for purification of the primary eluate of ⁶⁸ Ge-⁶⁸ Ga generator by using a small cation exchange resin (Dowex-50) column has been described. The breakthrough of ⁶⁸ Ge before and after purification of ⁶⁸ Ga eluate was 0.014% and 0.00027%, respectively. The average recovery yield of ⁶⁸ Ga after purification was 84% ± 8.6% (SD, n = 335). The results of the physiochemical studies confirmed that the ⁶⁸ Ga-acetate obtained is suitable for labeling of radiopharmaceuticals.

[Manufacture and Utilization of a Low-level Radioactive 68Ge/68Ga Generator in a Radiochemistry Laboratory Course]

The low-level radioactivity of a (68)Ge/(68)Ga generator is a suitable tool for measuring radioactive growth and decay after (68)Ga milking due to their desirable nuclear decay properties, such as the EC decay of (68)Ge with no γ-ray emission andthe β(+) decay of (68)Ga with a weak γ-ray emission. To experience andund erstandrad ioactive equilibrium during a university laboratory course, we surveyedandtestedthe production of a small amount of (68)Ge and set up educational programs to manufacture a (68)Ge/(68)Ga generator for measuring the growth andd ecay of (68)Ga. The irradiation of natGa with 25 μA of a 30 MeV proton beam from a cyclotron for 4 h yields ca. 111 MBq of (68)Ge, which was sufficient to supply to several universities. For use as the adsorbent of the generator column, particles of hydrated tin (VI) oxide were prepared from precipitated tin hydroxide gel. Repeated elution of (68)Ga from the handmade (68)Ge/(68)Ga generator gave constant amounts of (68)Ga with acceptable breakthrough of (68)Ge. The feedback from the student's experience with the (68)Ge/(68)Ga generator was evaluatedby annual questionnaire surveys, which were given to all students taking the course every year from 2012 to 2014. It has been made clear that more than half of the students were interested in the (68)Ge/(68)Ga generator program, andthis interest increasedfrom 54.9%in 2012 to 78.6%in 2014. A low-level radioactive (68)Ge/(68)Ga generator is thus expectedto be a suitable experimental tool for demonstrating the phenomenon of radioactivity to students in an intriguing way.

68Ga-Based radiopharmaceuticals: production and application relationship

The contribution of ⁶⁸Ga to the promotion and expansion of clinical research and routine positron emission tomography (PET) for earlier better diagnostics and individualized medicine is considerable. The potential applications of ⁶⁸Ga-comprising imaging agents include targeted, pre-targeted and non-targeted imaging. This review discusses the key aspects of the production of ⁶⁸Ga and ⁶⁸Ga-based radiopharmaceuticals in the light of the impact of regulatory requirements and endpoint pre-clinical and clinical applications.