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Analysis of 237Np in spent fuel solutions
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A. Morgenstern
Veröffentlicht/Copyright:
25. September 2009
Summary
An experimental procedure has been developed for the analysis of neptunium in input solutions of spent nuclear fuel reprocessing. The method consists of selective chromatographic extraction of neptunium and plutonium using TEVA resin followed by determination of the ratio of [Np]/[Pu] on the column by high-resolution gamma spectrometry. Knowing the concentration of plutonium from routinely performed K-edge densitometry and X-ray fluorescence measurements, the concentration of Np can be evaluated. The method has been tested on simulated solutions and validated on spent fuel of known [Np]/[Pu] ratio.
Received: 2002-2-21
Accepted: 2002-3-11
Published Online: 2009-9-25
Published in Print: 2002-7-1
© Oldenbourg Wissenschaftsverlag, München
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- 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
