Quantitative measurement of fission and activation products resulting from neutron irradiation of fissile materials is of
interest for applications in environmental monitoring, nuclear waste management, and national security. Based on established
separation processes involving co-precipitation, solvent extraction, and ion-exchange and extraction chromatography, we have
optimized a proposed sequence of separation steps to allow for the timely quantification of analytes of interest. We have
recently evaluated this scheme using an irradiated sample to examine the adequacy of separations for measurement of desired
analytes by gamma spectrometry. Here we present the radiochemical separations utilized and the yields and purity obtained.