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The separation of99Tc from mixed fission products and its determination by neutron activation
Authors:B. J. Mincher  J. D. Baker
Affiliation:(1) Idaho National Engineering Laboratory, Chemical Science Group, EG&G Idaho, Inc., 83415 Idaho Falls, Idaho, (USA)
Abstract:Technetium is separated from the bulk of fission products and other elements in dissolved nuclear fuel by a ferric hydroxide precipitation followed by filtration and loading of the filtrate on an anion exchange resin. The technetium remains on the resin presumably as pertechnate ion. The resin is exposed to a neutron flux in a nuclear reactor activating99Tc to100Tc which decays with the emission of a 539keV gamma-ray with a 15.8 second half-life. This gamma-ray is conveniently counted with conventional solid state techniques.Work performed under contract to the U. S. Department of Energy under contract number DE-ACO7-76IDO1570.
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