Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
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S. Busse
Summary
The radioisotope 90Nb is a positron emitter with a relatively high positron branching of 51% and a rather low β+-energy of Emean = 662 keV Emax = 1.5 MeV) with potential for application in positron emission tomography (PET). Its half-life of 14.6 h makes it especially promising for the quantitative investigation of biological processes with slow distribution kinetics. An advantageous production route of 90Nb is the natZr(p, n)90Nb process. To separate nca (no-carrier-added) radioniobium from macroscopic amounts of irradiated zirconium targets, an effective two step separation procedure was developed. A liquid-liquid extraction using N-benzoyl-N-phenylhydroxylamine (BPHA) in CHCl3 was applied first to separate the bulk of the zirconium matrix with a Zr separation coefficient of about 104, followed by anion-exchange chromatography for high grade purification of nca radioniobium. A sufficiently high decontamination factor of > 2 × 107 and an overall radiochemical yield of nca 90Nb of about 70% was achieved within about 3 hours.
© Oldenbourg Wissenschaftsverlag, München
Artikel in diesem Heft
- 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
Artikel in diesem Heft
- 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
