Radiochemical determination of fission products of uranium |
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Authors: | R Cornelis A Speecke J Hoste |
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Institution: | (1) Institute for Nuclear Sciences, Ghent University, Belgium |
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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.
Research associate of the I. I. K. W. |
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