Abstract
A semi-automated purification module for the cyclic separation of 99mTc was designed for production of [99mTc]TcO4– from γ irradiated 100Mo target. The separation process was carried out by using a 3-column purification system and the final product, [99mTc]TcO4–, was obtained in a total volume of 7 mL. To confirm proper separation achieved for 99mTc, a radio-labeling procedure using DTPA chelator was performed. The radiochemical purity was higher than 95%, which meets the strict radiopharmaceutical requirements. The yielded 99mTc can be separated with high efficiency from Mo in a quick and repeated way. Loss of 99mTc radioactivity during such a three-column separation process was not larger than 10%.
Highlights
The radionuclide technetium-99 m (99mTc) is a gamma emitter ideal for diagnostic applications due to its realatively short half-life (t1/2 = 6.0 h) and the emitted photon energy (γ = 140.5 keV) which are well suited for Single-Photon Emission Computed Tomography (SPECT) imaging In addition, it allows for exploiting its multi-oxidation states resulting in the ability to produce a variety of complexes
The separation system we propose concerns a 100Mo target irradiated with gamma quanta, where as a result of the nuclear reaction 99Mo the parent radionuclide for 99mTc is produced
A semi-automated module prototype set up for the separation and use of 99mTc radionuclide yielded by decay of parent 99Mo, obtained from 100Mo targets irradiated by high-energy gamma beams is here described, along with subsequent extraction of [99mTc]TcO4– from Mo using new AnaLig® Tc-02 extraction resin
Summary
The design and development of a separation system is described, based upon column chromatography with an AnaLig®Tc-02 resin for the isolation of 99mTc from 100Mo target irradiated with high energy γ photons. The aim of this study was to set up a semi-automated purification module for cyclic [99mTc]TcO4– separation 100Mo-enriched target irradiated by a gamma beam This is the first study, where AnaLig®Tc-02 resin has been used to construct a 99mTc generator from the low specific activity 99Mo. AnaLig® Tc-02 was purchased from IBC Advanced Technologies Inc. The process of separation of 99mTc from Mo target was tested on a solution simulating a dissolved 100Mo target irradiated with a gamma beam For this purpose, we used natMo (≥ 99.99%, Merck) and [99mTc]TcO4– eluate obtained from Polgentec 99Mo/99mTc isotope generator (POLATOM, Poland). Fig. 2. 99mTc elution curves from AnaLig® Tc-02 resin depending on the flow rate of the eluent. (filled square) loading flow rate was 0.2 mL/min and flow rate of water (to elute [99mTc]TcO4−): 0.2–1 mL/min, (filled circle)loading flow rate was 0.2 mL/min and flow rate of water (to elute[99mTc]TcO4–): 0.5 mL/min, (filled triangle) loading flow rate was 0.4 mL/min and flow rate of water (to elute [99mTc]TcO4–): 0.4 mL/min
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