A novel electrochemical 99Mo/99mTc generator

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear Installations16080View full textAdd to dashboardCite

“…The 99m Tc electrodeposit and the followed pertechnetate recovery were performed at the voltage 5 V (current 500 mA and current density 300 mA/cm 2 ) and 10 V (reversed polarity), respectively. Postelectrolysis purification of 99m Tc solution was also completed with an alumina column [117,118].…”

An overview of radioisotope separation technologies for development of 188W/188Re radionuclide generators providing 188Re to meet future research and clinical demands

“…Electrochemical separation exploits the differences in the standard reduction potential of metal ions to separate metal ions of interest under the inuence of an applied potential. [117][118][119][120][121][122][123][124][125] This separation technique is expected to be poised to In this process, the potential of the working electrode is maintained constant (or within a narrow range) by regulation of the voltage applied in such a way to permit the quantitative deposition (by reduction) of 188 Re on an electrode surface, from a suitable electrolyte solution containing the 188 W/ 188 Re equilibrium mixture. 125 A schematic diagram of the electrochemical set up used for the separation of 188 Re is shown in Fig.…”

Pivotal role of separation chemistry in the development of radionuclide generators to meet clinical demands

“…153 The rst use of the electrochemical separation approach for the preparation of radionuclide generators was reported by Chakravarty et al 154 The authors reported the development of the 90 Sr/ 90 Y generator for the separation of clinical grade 90 Y from long lived 90 Sr. 154 The technology was further extended to other parent/daughter systems, such as 188 W/ 188 Re, 99 Mo/ 99m Tc, etc., by the same group of authors. [155][156][157] The exquisite sensitivity and specicity of the electrochemical technique not only provides daughter radionuclides of the requisite purity, but also offer the scope of using low specic activity parent radionuclides (neutron activated 99 Mo or 188 W) for the preparation of clinical-scale generators, and also eliminates the need for a post-elution concentration procedure prior to radiopharmaceutical preparation.…”