Separation of radioactive terbium from massive Gd targets for medical use

Brezovcsik, Károly; Szelecsényi, F.

doi:10.1007/s10967-018-5718-3

Cited by 5 publications

(2 citation statements)

References 13 publications

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“…Recently, Brezovcsik et al reported a Tb separation procedure from massive Gd targets (> 100 mg) using a 20 cm long analytical HPLC column (GE), indicating no mass influence of Gd on the separation process (Brezovcsik 2018). The efficiency of Tb separation from Gd was only 85%, however, showing significant overlapping of Tb and Gd peaks, which would result in the presence of “cold” Gd in the Tb final product and significantly decrease radiolabeling efficiency.…”

Section: Discussionmentioning

confidence: 99%

Production and characterization of no-carrier-added 161Tb as an alternative to the clinically-applied 177Lu for radionuclide therapy

Gracheva

Müller

Talip

et al. 2019

EJNMMI radiopharm. chem.

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Background 161 Tb is an interesting radionuclide for cancer treatment, showing similar decay characteristics and chemical behavior to clinically-employed 177 Lu. The therapeutic effect of 161 Tb, however, may be enhanced due to the co-emission of a larger number of conversion and Auger electrons as compared to 177 Lu. The aim of this study was to produce 161 Tb from enriched 160 Gd targets in quantity and quality sufficient for first application in patients. Methods No-carrier-added 161 Tb was produced by neutron irradiation of enriched 160 Gd targets at nuclear research reactors. The 161 Tb purification method was developed with the use of cation exchange (Sykam resin) and extraction chromatography (LN3 resin), respectively. The resultant product ( 161 TbCl 3 ) was characterized and the 161 Tb purity compared with commercial 177 LuCl 3 . The purity of the final product ( 161 TbCl 3 ) was analyzed by means of γ-ray spectrometry (radionuclidic purity) and radio TLC (radiochemical purity). The radiolabeling yield of 161 Tb-DOTA was assessed over a two-week period post processing in order to observe the quality change of the obtained 161 Tb towards future clinical application. To understand how the possible drug products (peptides radiolabeled with 161 Tb) vary with time, stability of the clinically-applied somatostatin analogue DOTATOC, radiolabeled with 161 Tb, was investigated over a 24-h period. The radiolytic stability experiments were compared to those performed with 177 Lu-DOTATOC in order to investigate the possible influence of conversion and Auger electrons of 161 Tb on peptide disintegration. Results Irradiations of enriched 160 Gd targets yielded 6–20 GBq 161 Tb. 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 161 Tb or 177 Lu 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 161 Tb or 177 Lu, was stable over 24 h in the presence of a stabilizer. Conclusions In this study, it was shown that 161 Tb can be produced in hig...

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Section: Discussionmentioning

confidence: 99%

Production and characterization of no-carrier-added 161Tb as an alternative to the clinically-applied 177Lu for radionuclide therapy

Gracheva

Müller

Talip

et al. 2019

EJNMMI radiopharm. chem.

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“…Besides the application of the spallation process to the production of 152 Tb, many investigations on other possible production reactions have also been carried out. They deal either with cross section measurements of proton and deuteron induced reactions on gadolinium and dysprosium [161][162][163][164][165][166] or with chemical separation of radioterbium from gadolinium irradiated with protons [167], europium irradiated with α-particles [168] or lanthanum and cerium irradiated with 16 O-ions [169,170]. The (p,xn) reactions on gadolinium isotopes in the intermediate energy range appear to be promising.…”

Section: Development Of 152 Tb and 149 Tbmentioning

confidence: 99%

New developments in the production of theranostic pairs of radionuclides

Qaim

Schölten

Neumaier

2018

J Radioanal Nucl Chem

132

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A brief historical background of the development of the theranostic approach in nuclear medicine is given and seven theranostic pairs of radionuclides, namely 44g Sc/ 47 Sc, 64 Cu/ 67 Cu, 83 Sr/ 90 Sr, 86 Y/ 90 Y, 124 I/ 131 I, 152 Tb/ 161 Tb and 152 Tb/ 149 Tb, are considered. The first six pairs consist of a positron and a β −-emitter whereas the seventh pair consists of a positron and an α-particle emitter. The decay properties of all those radionuclides are briefly mentioned and their production methodologies are discussed. The positron emitters 64 Cu, 86 Y and 124 I are commonly produced in sufficient quantities via the (p,n) reaction on the respective highly enriched target isotope. A clinical scale production of the positron emitter 44g Sc has been achieved via the generator route as well as via the (p,n) reaction, but further development work is necessary. The positron emitters 83 Sr and 152 Tb are under development. Among the therapeutic radionuclides, 89 Sr, 90 Y and 131 I are commercially available and 161 Tb can also be produced in sufficient quantity at a nuclear reactor. Great efforts are presently underway to produce 47 Sc and 67 Cu via neutron, photon and charged particle induced reactions. The radionuclide 149 Tb is unique because it is an α-particle emitter. The present method of production of 152 Tb and 149 Tb involves the use of the spallation process in combination with an on-line mass separator. The role of some emerging irradiation facilities in the production of special radionuclides is discussed.

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