Abstract
An analysis has been elaborated to determine the long-living γ-emitting fission products of uranium. It consists of a sodium bisulphate melt of the fission product solution or the U-fuel, followed by liquid-liquid extractions. Afterwards the isotopes are absolutely counted with a standardized 3″×3″ NaI crystal. The total γ-spectrum of the original fission product solution, taken with a NaI crystal or a Ge−Li detector, is also analyzed mathematically by mixed γ-spectrometry. From a short post-irradiation of the fission product solution the concentrations of both235U and238U are determined. The absolute amount of fission products related to the U-concentration allows the calculation of the percent atomic burn-up, the irradiation time, the cooling period, the flux of the reactor and the original degree of enrichment of the uranium.
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Research associate of the I. I. K. W.
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Cornelis, R., Speecke, A. & Hoste, J. Radiochemical determination of fission products of uranium. J. Radioanal. Chem. 1, 5–24 (1968). https://doi.org/10.1007/BF02513578
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DOI: https://doi.org/10.1007/BF02513578