Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
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S. Chattopadhyay
Summary
A novel method for the recovery of 99mTcO4− from (n, γ)99Mo using conventional anion-exchange chromatography over Dowex-1 × 8 column, followed by elution and subsequent novel purification over AgCl-alumina column is reported. 99MoO42− 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. 99mTcO4− preferentially retained on the Dowex-1 column, was recovered quantitatively by elution with 4 ml of 4 M HNO3 or 4 ml 0.2 M HClO4 or 6 ml of 0.2 M NaI solution. Further purification to deliver 99mTcO4− 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 99mTcO4− was 75%−85% and the quality features of 99mTcO4− were compatible to radiopharmaceutical use. The method has applicability for decontamination of 99gTc from spent 99Mo waste solution and recovery of 99gTc for research use. The procedure should also be equally applicable for recovery of 188ReO4− from 188WO42− in a radioisotope laboratory.
© Oldenbourg Wissenschaftsverlag, München
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- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
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- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
- Synthesis, radiolabelling characteristics and biological evaluation of the derivatives of mercaptoacetyltriglycine
Articles in the same Issue
- Photofission of 209Bi at intermediate energies
- Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
- Analysis of 237Np in spent fuel solutions
- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
- Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water
- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
- Synthesis, radiolabelling characteristics and biological evaluation of the derivatives of mercaptoacetyltriglycine
