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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]

44Sc is a promising positron emission tomography (PET) radionuclide (T1/2 = 4.04 hours, Eβ+average = 632 keV) and can be made available, using a cyclotron production route, in substantial quantities as a highly pure product. Herein, the authors report on a first-in-human PET/CT study using 44Sc-DOTATOC prepared with cyclotron-produced 44Sc. The production of 44Sc was carried out through the 44Ca(p,n)44Sc nuclear reaction at Paul Scherrer Institut, Switzerland. After separation, 44Sc was shipped to Zentralklinik Bad Berka, Germany, where radiolabeling was performed, yielding radiochemically pure 44Sc-DOTATOC. Two patients, currently followed up after peptide receptor radionuclide therapy of metastatic neuroendocrine neoplasms, participated in this proof-of-concept study. Blood sampling was performed before and after application of 44Sc-DOTATOC. PET/CT acquisitions, performed at different time points after injection of 44Sc-DOTATOC, allowed detection of even very small lesions on delayed scans. No clinical adverse effects were observed and the laboratory hematological, renal, and hepatic profiles remained unchanged. In this study, cyclotron-produced 44Sc was used in the clinic for the first time. It is attractive for theranostic application with 177Lu, 90Y, or 47Sc as therapeutic counterparts. 44Sc-based radiopharmaceuticals will be of particular value for PET facilities without radiopharmacy, to which they can be shipped from a centralized production site. [ABSTRACT FROM AUTHOR]

Introduction 44 Sc, a PET radionuclide, has promising decay characteristics (T 1/2 = 3.97 h, Eβ + av = 632 keV) for nuclear imaging and is an attractive alternative to the short-lived 68 Ga (T 1/2 = 68 min, Eβ + av = 830 keV). The aim of this study was the optimization of the 44 Sc production process at an accelerator, allowing its use for preclinical and clinical PET imaging. Methods 44 CaCO 3 targets were prepared and irradiated with protons (~ 11 MeV) at a beam current of 50 μA for 90 min. 44 Sc was separated from its target material using DGA extraction resin and concentrated using SCX cation exchange resin. Radiolabeling experiments at activities up to 500 MBq and stability tests were performed with DOTANOC by investigating different scavengers, including gentisic acid. Dynamic PET of an AR42J tumor-bearing mouse was performed after injection of 44 Sc-DOTANOC. Results The optimized chemical separation method yielded up to 2 GBq 44 Sc of high radionuclidic purity. In the presence of gentisic acid, radiolabeling of 44 Sc with DOTANOC was achieved with a radiochemical yield of ~ 99% at high specific activity (10 MBq/nmol) and quantities which would allow clinical application. The dynamic PET images visualized increasing uptake of 44 Sc-DOTANOC into AR42J tumors and excretion of radioactivity through the kidneys of the investigated mouse. Conclusions The concept “from-bench-to-bedside” was clearly demonstrated in this extended study using cyclotron-produced 44 Sc. Sufficiently high activities of 44 Sc of excellent radionuclidic purity are obtainable for clinical application, by irradiation of enriched calcium at a cyclotron. This work demonstrates a promising basis for introducing 44 Sc to clinical routine of nuclear imaging using PET. [ABSTRACT FROM AUTHOR]