Recovery of 201Tl by ion exchange chromatography from proton bombarded thallium cyclotron targets
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T.N. van der Walt
A method based on ion exchange chromatography is presented for the recovery of 201Tl and its precursor 201Pb from proton bombarded natural thallium cyclotron targets. After bombardment the target is dissolved in diluted nitric acid. Water, hydrazine and ammonium acetate are added to the solution and the lead radioisotopes separated from the thallium by cation exchange chromatography on a Bio-Rex 70 column. The sorbed lead radioisotopes are eluted with dilute nitric acid and the separation repeated on a second Bio-Rex 70 column. After elution of the remaining thallium the column is left for 32 hours and the 201Tl formed by decay of 201Pb is eluted with an ammonium acetate solution. The 201Tl eluate is acidified with a HNO3-HBr-Br2 mixture and the resulting solution is passed through an AG MP-1 anion exchanger column to remove any remaining lead isotopes. The 201Tl is eluted with a hydrazine solution, the eluate evaporated to dryness and the 201Tl finally dissolved in an appropiate solution to produce a 201TlCl solution suitable for medical use. A high quality 201Tl product is obtained containing ≤0.1 μg of Tl/mCi (37 MBq) 201Tl. The radionuclidic impurities are less than the maximum values specified by the US Pharmacopoeia and the British Pharmacopoeia.
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Articles in the same Issue
- Preface: Alfred P. Wolf Memorial Issue
- Im Memoriam Alfred P. Wolf
- The centenary of a controversial discovery: actinium
- Proton-induced nuclear reactions in neptunium-237 targets. Production of plutonium tracers in the energy range 15-40 MeV
- Possibility of production of 81Rb via the 80Kr(d,n) reaction at a small cyclotron
- Positron emission intensity in the decay of 120gI
- Production of high specific activity 27Mg by fast neutron irradiation and recoil-aided leaching
- Production of strontium-82 for the Cardiogen® PET generator: a project of the Department of Energy Virtual Isotope Center
- Lutetium-177-EDTMP for bone pain palliation. Preparation, biodistribution and pre-clinical studies
- Thermochromatographic separation of no-carrier-added 186Re or 188Re from tungsten targets relevant to nuclear medical applications
- Low energy cyclotron production and chemical separation of "no carrier added" iodine-124 from a reusable, enriched tellurium-124 dioxide/aluminum oxide solid solution target
- Physicochemical and radiochemical aspects of separation of radioiodine from TeO2-targets
- Novel separation of thallium-201 using p-tert-butylcalix[4]arene derivative
- Recovery of 201Tl by ion exchange chromatography from proton bombarded thallium cyclotron targets
- Doppler broadening as a probe of the chemical environment following oxygen-14 decay
- In-target chemistry during the production of 15O and 11C using 3He reactions
- 11C-methane production in small volume, high pressure gas targets
- 11C-methylations using 11C-methyl iodide and tetrabutylammonium fluoride
- Specific activity of [11C]CO2 generated in a N2 gas target: effect of irradiation dose, irradiation history, oxygen content and beam energy
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- Direct n.c.a. radioiodination of weakly activated arenes using metal salts
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- EXAFS analyses of technetium(I) carbonyl complexes – stability studies in solutions
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