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Background: 64Cu (T1/2 = 12.7 h) is an important radionuclide for diagnostic purposes and used for positron emission tomography (PET). A previous method utilized at Paul Scherrer Institute (PSI) proved to be unreliable and, while a method using anion exchange chromatography is a popular choice worldwide, it was felt a different approach was required to obtain a robust chemical separation method. Methods: Enriched 64Ni targets were created by electroplating on gold foil. The targets were irradiated with protons degraded to approximately 11 MeV at PSI's Injector 2 72 MeV research cyclotron and subsequently dissolved in HCl. The resultant solution was loaded onto AG MP‐50 cation exchange resin and the 64Cu separated from its target material and radiocobalt impurities, produced as part of the irradiation process, using various specific mixtures of HCl/acetone solution. The eluted product was evaporated and picked up in dilute HCl (0.05 M). The chemical purity of 64Cu was determined by radiolabeling experiments at the highest possible molar activities. Results: Reproducible results were obtained, yielding 3.6 to 8.3 GBq 64Cu of high radionuclidic and radiochemical purity. The product was labeled to NODAGA‐RGD, achieved at up to 500 MBq/nmol, indicating the high chemical purity. In a proof‐of‐concept in vivo study, 64Cu‐NODAGA‐RGD was used for PET imaging of a tumor‐bearing mouse. Conclusion: The chemical separation devised to produce high‐quality 64Cu proved to be robust and reproducible. The concept can be used at medical cyclotrons utilizing a solid target station, such that 64Cu can be used at hospitals for PET imaging. [ABSTRACT FROM AUTHOR]

Background: The favorable decay properties of Sc and Sc for PET make them promising candidates for future applications in nuclear medicine. An advantage Sc (T = 3.89 h, Eβ = 476 keV [88%]) exhibits over Sc, however, is the absence of co-emitted high energy γ-rays. While the production and application of Sc has been comprehensively discussed, research concerning Sc is still in its infancy. This study aimed at developing two different production routes for Sc, based on proton irradiation of enriched Ti and Ca target material. Results: Sc was produced via the Ti(p,α)Sc and Ca(p,n)Sc nuclear reactions, yielding activities of up to 225 MBq and 480 MBq, respectively. Sc was chemically separated from enriched metallic Ti (97.0%) and CaCO (57.9%) targets, using extraction chromatography. In both cases, ~90% of the final activity was eluted in a small volume of 700 μL, thereby, making it suitable for direct radiolabeling. The prepared products were of high radionuclidic purity, i.e. 98.2% Sc were achieved from the irradiation of Ti, whereas the product isolated from irradiated Ca consisted of 66.2% Sc and 33.3% Sc. A PET phantom study performed with Sc, via both nuclear reactions, revealed slightly improved resolution over Sc. In order to assess the chemical purity of the separated Sc, radiolabeling experiments were performed with DOTANOC, attaining specific activities of 5-8 MBq/nmol, respectively, with a radiochemical yield of >96%. Conclusions: It was determined that higher Sc activities were accessible via the Ca production route, with a comparatively less complex target preparation and separation procedure. The product isolated from irradiated Ti, however, revealed purer Sc with minor radionuclidic impurities. Based on the results obtained herein, the Ca route features some advantages (such as higher yields and direct usage of the purchased target material) over the Ti path when aiming at Sc production on a routine basis. [ABSTRACT FROM AUTHOR]

The existence of theragnostic pairs of radionuclides allows the preparation of radiopharmaceuticals for diagnostic and therapeutic purposes. Radiolanthanides, such as 177Lu, are successfully used for therapeutic purposes; however, a perfect diagnostic match is currently not available for clinical use. A unique, multi-disciplinary study was performed using 152Tb (T1/2 = 17.5 h, Eβ+average = 1140 keV, Iβ+ = 20.3%), which resulted in the first-in-human PET/CT images with this promising radionuclide. For this purpose, 152Tb was produced via a spallation process followed by mass separation at ISOLDE, CERN. The chemical separation and quality control, performed at PSI, resulted in a pure product in sufficient yields. Clinical PET phantom studies revealed an increased image noise level, because of the smaller β+ branching ratio of 152Tb as compared to standard PET nuclides at matched activity concentrations; however, the expected recovery would be comparable at matched signal-to-noise ratios in clinical PET. 152Tb was used for labeling DOTATOC, at Zentralklinik Bad Berka, and administered to a patient for a first-in-human clinical study. PET scans were performed over a period of 24 h, allowing the visualization of even small metastases with increased tumor-to-background contrast over time. Based on the results obtained in this work, it can be deduced that PET/CT imaging with 152Tb-labeled targeting agents has promise for clinical application and may be particularly interesting for pre-therapeutic dosimetry. [ABSTRACT FROM AUTHOR]

Background: Radiotheragnostics makes use of the same molecular targeting vectors, labeled either with a diagnostic or therapeutic radionuclide, ideally of the same chemical element. The matched pair of scandium radionuclides, Sc and Sc, satisfies the desired physical aspects for PET imaging and radionuclide therapy, respectively. While the production and application of Sc was extensively studied, Sc is still in its infancy. The aim of the present study was, therefore, to investigate and compare two different methods of Sc production, based on the neutron irradiation of enriched Ca and Ti targets, respectively. Methods: Sc was produced by thermal neutron irradiation of enriched Ca targets via the Ca(n,γ)Ca → Sc nuclear reaction and by fast neutron irradiation of Ti targets via the Ti(n,p)Sc nuclear reaction, respectively. The product was compared with regard to yield and radionuclidic purity. The chemical separation of Sc was optimized in order to obtain a product of sufficient quality determined by labeling experiments using DOTANOC. Finally, preclinical SPECT/CT experiments were performed in tumor-bearing mice and compared with the PET image of the Sc labeled counterpart. Results: Up to 2 GBq Sc was produced by thermal neutron irradiation of enriched Ca targets. The optimized chemical isolation of Sc from the target material allowed formulation of up to 1.5 GBq Sc with high radionuclidic purity (>99.99%) in a small volume (~700 μL) useful for labeling purposes. Three consecutive separations were possible by isolating the in-grown Sc from the Ca-containing fraction. Sc produced by fast neutron irradiated Ti targets resulted in a reduced radionuclidic purity (99.95-88.5%). The chemical purity of the separated Sc was determined by radiolabeling experiments using DOTANOC achievable at specific activities of 10 MBq/nmol. In vivo the Sc-DOTANOC performed equal to Sc-DOTANOC as determined by nuclear imaging. Conclusion: The production of Sc via the Ca(n,γ)Ca nuclear reaction demonstrated significant advantages over the Ti production route, as it provided higher quantities of a radionuclidically pure product. The subsequent decay of Ca enabled the repeated separation of the Sc daughter nuclide from the Ca parent nuclide. Based on the results obtained from this work, Sc shows potential to be produced in suitable quality for clinical application. [ABSTRACT FROM AUTHOR]

Background: The targeting of the prostate-specific membrane antigen (PSMA) is of particular interest for radiotheragnostic purposes of prostate cancer. Radiolabeled PSMA-617, a 1,4,7,10-tetraazacyclododecane- N, N′, N′′, N′′′-tetraacetic acid (DOTA)-functionalized PSMA ligand, revealed favorable kinetics with high tumor uptake, enabling its successful application for PET imaging (Ga) and radionuclide therapy (Lu) in the clinics. In this study, PSMA-617 was labeled with cyclotron-produced Sc ( T = 4.04 h) and investigated preclinically for its use as a diagnostic match to Lu-PSMA-617. Results: Sc was produced at the research cyclotron at PSI by irradiation of enriched Ca targets, followed by chromatographic separation. Sc-PSMA-617 was prepared under standard labeling conditions at elevated temperature resulting in a radiochemical purity of >97% at a specific activity of up to 10 MBq/nmol. Sc-PSMA-617 was evaluated in vitro and compared to the Lu- and Ga-labeled match, as well as Ga-PSMA-11 using PSMA-positive PC-3 PIP and PSMA-negative PC-3 flu prostate cancer cells. In these experiments it revealed similar in vitro properties to that of Lu- and Ga-labeled PSMA-617. Moreover, Sc-PSMA-617 bound specifically to PSMA-expressing PC-3 PIP tumor cells, while unspecific binding to PC-3 flu cells was not observed. The radioligands were investigated with regard to their in vivo properties in PC-3 PIP/flu tumor-bearing mice. Sc-PSMA-617 showed high tumor uptake and a fast renal excretion. The overall tissue distribution of Sc-PSMA-617 resembled that of Lu-PSMA-617 most closely, while the Ga-labeled ligands, in particular Ga-PSMA-11, showed different distribution kinetics. Sc-PSMA-617 enabled distinct visualization of PC-3 PIP tumor xenografts shortly after injection, with increasing tumor-to-background contrast over time while unspecific uptake in the PC-3 flu tumors was not observed. Conclusions: The in vitro characteristics and in vivo kinetics of Sc-PSMA-617 were more similar to Lu-PSMA-617 than to Ga-PSMA-617 and 68Ga-PSMA-11. Due to the almost four-fold longer half-life of Sc as compared to Ga, a centralized production of Sc-PSMA-617 and transport to satellite PET centers would be feasible. These features make Sc-PSMA-617 particularly appealing for clinical application. [ABSTRACT FROM AUTHOR]