Medical radionuclides such as Ga-68, Cu-64 or Ac-225 are usually produced by irradiation of enriched target materials in cyclotrons or nuclear reactors. After irradiation, the radionuclides need to be separated from their target. While this is mostly done by ion-exchange chromatography, an emerging separation method includes the use of (microfluidic) solvent extraction. However, the extent to which the chelators and organic solvents used during solvent extraction contaminate the final radionuclide-containing solution, including their potential impact on subsequent radiolabeling applications, has not been studied in detail. In this study, the potential contaminants N-benzoyl-N-phenylhydroxilamine (BPHA), dithizone (DIZ) and di(2-ethylhexyl)phosphoric acid (D2EHPA) were investigated, and a microcolumn purification method is proposed. It was found that contaminations with two of these chelators, BPHA and DIZ, significantly interfered with DOTA (1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid) labeling. The applied microcolumn purification method eliminated the BPHA contamination from the Ga-68 solution completely, while simultaneously drastically reducing the total volume and acidity of the solution. It is therefore a promising purification method that can be included in an automated microfluidic solvent extraction procedure.

Chelator-impregnated resins have been studied earlier for the chemical separation of elements in aqueous solutions, but issues with their chemical stability have limited their use in the separation of (medical) radionuclides from their respective irradiated targets. We developed a polydimethylsiloxane (PDMS)-based chelator-impregnated resin that showed a high chemical stability against leaching. Several different chelators were tested in this study. After impregnation of the PDMS beads with the di-2-ethylhexylphosphoric acid (D2EHPA) chelator, an in-flow separation study with various radionuclides (Y-90, La-140, and Ac-225) was conducted. These three radionuclides have potential use in nuclear medicine and a production route through irradiation of Sr-, Ba-, and Ra-targets respectively, necessitating their chemical separation. The D2EHPA-impregnated beads achieved high adsorption efficiencies of 99.89% ± 0.14%, 99.50% ± 0.10%, and 98.51% ± 0.25%, for Y-90, La-140, and Ac-225, respectively, while co-adsorption of minor amounts (< 3%) of the targets were reported. These results, together with the high chemical stability of the PDMS-based resin, highlight the potential of chelator-impregnated resins in the rapidly growing field of (medical) radionuclide production.

Separating medical radionuclides from their targets is one of the most critical steps in radiopharmaceutical production. Among many separation methods, solvent extraction has a lot of potential due to its simplicity, high selectivity, and high efficiency. Especially with the rise of polydimethylsiloxane (PDMS) microfluidic chips, this extraction process can take place in a simple and reproducible chip platform continuously and automatically. Furthermore, the microfluidic chips can be coated with metal-oxide nano-layers, increasing their resistance against the employed organic solvents. We fabricated such chips and demonstrated a parallel flow at a considerably large range of flow rates using the aqueous and organic solutions commonly used in medical radionuclide extraction. In our following case study for the separation of Ac-225 from radium with the chelator di(2-ethylhexyl)phosphoric acid (D2EHPA), a remarkable extraction efficiency of 97.1 % ± 1.5 % was reached within 1.8 seconds of contact time, while maintaining a near perfect phase separation of the aqueous and organic solutions. This method has the potential to enable automation of solvent extraction and faster target recycling, and serves, therefore, as a proof-of-concept for the applicability of microfluidic chip solvent extraction of (medical) radionuclides.

Background: The radionuclide Ga-68 is commonly used in nuclear medicine, specifically in positron emission tomography (PET). Recently, the interest in producing Ga-68 by cyclotron irradiation of [⁶⁸Zn]Zn nitrate liquid targets is increasing. However, current purification methods of Ga-68 from the target solution consist of multi-step procedures, thus, leading to a significant loss of activity through natural decay. Additionally, several processing steps are needed to recycle the costly, enriched target material. Results: To eventually allow switching from batch to continuous production, conventional batch extraction and membrane-based microfluidic extraction were compared. In both approaches, Ga-68 was extracted using N-benzoyl-N-phenylhydroxylamine in chloroform as the organic extracting phase. Extraction efficiencies of up to 99.5% ± 0.6% were achieved within 10 min, using the batch approach. Back-extraction of Ga-68 into 2 M HCl was accomplished within 1 min with efficiencies of up to 94.5% ± 0.6%. Membrane-based microfluidic extraction achieved 99.2% ± 0.3% extraction efficiency and 95.8% ± 0.8% back-extraction efficiency into 6 M HCl. When executed on a solution irradiated with a 13 MeV cyclotron at TRIUMF, Canada, comparable efficiencies of 97.0% ± 0.4% were achieved. Zn contamination in the back-extracted Ga-68 solution was found to be below 3 ppm. Conclusions: Microfluidic solvent extraction is a promising method in the production of Ga-68 achieving high efficiencies in a short amount of time, potentially allowing for direct target recycling. Graphical Abstract: [Figure not available: see fulltext.].