Description: Direct alpha counting to determine fissile material in dilnte solutions of high total solids content is likely to be inaccurate due to the difficulty of preparing thin sources. This report describes a neutron-activation analysis method which eliminates this risk. Results obtained by the neutronactivation analysis for U/sup 238/ in solution are compared with results obtained from other methods. The standard deviation and sensitivity are shown. (auth)
Date: August 1, 1957
Creator: Brown, P.E.; Davis, D.M. & Henley, L.C.
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