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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]

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: Recently, 44 Sc (T1/2 =3.97h,Eβ+av = 632 keV, I = 94.3 %) has emerged as an attractive radiometal candidate for PET imaging using DOTA-functionalized biomolecules. The aim of this study was to investigate the potential of using NODAGA for the coordination of 44Sc. Two pairs of DOTA/NODAGA-derivatized peptides were investigated in vitro and in vivo and the results obtained with 44Sc compared with its 68Ga-labeled counterparts. DOTA-RGD and NODAGA-RGD, as well as DOTA-NOC and NODAGA-NOC, were labeled with 44Sc and 68Ga, respectively. The radiopeptides were investigated with regard to their stability in buffer solution and under metal challenge conditions using Fe3+ and Cu2+. Time-dependent biodistribution studies and PET/CT imaging were performed in U87MG and AR42J tumor-bearing mice. Results: Both RGD- and NOC-based peptides with a DOTA chelator were readily labeled with 44Sc and 68Ga, respectively, and remained stable over at least 4 half-lives of the corresponding radionuclide. In contrast, the labeling of NODAGA-functionalized peptides with 44Sc was more challenging and the resulting radiopeptides were clearly less stable than the DOTA-derivatized matches. 44Sc-NODAGA peptides were clearly more susceptible to metal challenge than 44Sc-DOTA peptides under the same conditions. Instability of 68Ga-labeled peptides was only observed if they were coordinated with a DOTA in the presence of excess Cu2+. Biodistribution data of the 44Sc-labeled peptides were largely comparable with the data obtained with the 68Ga-labeled counterparts. It was only in the liver tissue that the uptake of 68Ga-labeled DOTA compounds was markedly higher than for the 44 Sc-labeled version and this was also visible on PET/CT images. The 44Sc-labeled NODAGA-peptides showed a similar tissue distribution to those of the DOTA peptides without any obvious signs of in vivo instability. Conclusions: Although DOTA revealed to be the preferred chelator for stable coordination of 44Sc, the data presented in this work indicate the possibility of using NODAGA in combination with 44 Sc. In view of a clinical study, thorough investigations will be necessary regarding the labeling conditions and storage solutions in order to guarantee sufficient stability of 44 Sc-labeled NODAGA compounds. [ABSTRACT FROM AUTHOR]

Tb represents a powerful alternative to currently used α-emitters: the relatively short half-life (T = 4.1 h), low α-energy (3.97 MeV, I = 16.7 %), absence of α-emitting daughters and stable coordination via DOTA are favorable features for potential clinical application. In this letter, we wish to highlight the unique characteristics of Tb for PET imaging, based on its positron emission (E = 730 keV, I = 7.1 %) in addition to it's a therapeutic value. To this end, a preclinical study with a tumor-bearing mouse is presented. The perspective of alpha-PET makes Tb highly appealing for radiotheragnostic applications in future clinical trials. [ABSTRACT FROM AUTHOR]

Background: 161Tb is an interesting radionuclide for cancer treatment, showing similar decay characteristics and chemical behavior to clinically-employed 177Lu. The therapeutic effect of 161Tb, however, may be enhanced due to the co-emission of a larger number of conversion and Auger electrons as compared to 177Lu. The aim of this study was to produce 161Tb from enriched 160Gd targets in quantity and quality sufficient for first application in patients. Methods: No-carrier-added 161Tb was produced by neutron irradiation of enriched 160Gd targets at nuclear research reactors. The 161Tb purification method was developed with the use of cation exchange (Sykam resin) and extraction chromatography (LN3 resin), respectively. The resultant product (161TbCl3) was characterized and the 161Tb purity compared with commercial 177LuCl3. The purity of the final product (161TbCl3) was analyzed by means of γ-ray spectrometry (radionuclidic purity) and radio TLC (radiochemical purity). The radiolabeling yield of 161Tb-DOTA was assessed over a two-week period post processing in order to observe the quality change of the obtained 161Tb towards future clinical application. To understand how the possible drug products (peptides radiolabeled with 161Tb) vary with time, stability of the clinically-applied somatostatin analogue DOTATOC, radiolabeled with 161Tb, was investigated over a 24-h period. The radiolytic stability experiments were compared to those performed with 177Lu-DOTATOC in order to investigate the possible influence of conversion and Auger electrons of 161Tb on peptide disintegration. Results: Irradiations of enriched 160Gd targets yielded 6–20 GBq 161Tb. The final product was obtained at an activity concentration of 11–21 MBq/μL with ≥99% radionuclidic and radiochemical purity. The DOTA chelator was radiolabeled with 161Tb or 177Lu at the molar activity deemed useful for clinical application, even at the two-week time point after end of chemical separation. DOTATOC, radiolabeled with either 161Tb or 177Lu, was stable over 24 h in the presence of a stabilizer. Conclusions: In this study, it was shown that 161Tb can be produced in high activities using different irradiation facilities. The developed method for 161Tb separation from the target material yielded 161TbCl3 in quality suitable for high-specific radiolabeling, relevant for future clinical application. [ABSTRACT FROM AUTHOR]