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A novel method for the recovery of  99m TcO 4  −  from (n, γ) 99 Mo using conventional anion-exchange chromatography over Dowex-1 × 8 column, followed by elution and subsequent novel purification over AgCl-alumina column is reported.  99 MoO 4  2−  solution (7 − 14 GBq/mg) in NaOH was passed down a Dowex-1 × 8 column (6 − 7 × 2 mm), collected and preserved for reuse on the subsequent days.  99m TcO 4  −  preferentially retained on the Dowex-1 column, was recovered quantitatively by elution with 4 ml of 4 M HNO 3  or 4 ml 0.2 M HClO 4  or 6 ml of 0.2 M NaI solution. Further purification to deliver  99m TcO 4  −  in a physiological vehicle has been achieved. Use of NaI eluent and post elution purification over a bed of 1 g AgCl + 1 g alumina developed has been adapted in preference to the other two eluents. The overall yield of  99m TcO 4  −  was 75%−85% and the quality features of  99m TcO 4  −  were compatible to radiopharmaceutical use. The method has applicability for decontamination of  99g Tc from spent  99 Mo waste solution and recovery of  99g Tc for research use. The procedure should also be equally applicable for recovery of  188 ReO 4  −  from  188 WO 4  2−  in a radioisotope laboratory.

radiochimica acta

Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of  99m Tc from ( n , γ) 99 Mo and suitability for use in central radiopharmacy (CRPh)