Abstract
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.
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Acknowledgements
We gratefully recognize funding by NA-22, Office of Nuclear Detonation Detection, Nonproliferation Research and Development, National Nuclear Security Administration, U.S. Department of Energy, and Director Randy Bell. We thank Don Wall of the Dodgen Research Facility and Nuclear Radiation Center at Washington State University for his assistance with the neutron irradiation of HEU and production of activation product radionuclides.
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Douglas, M., Friese, J.I., Greenwood, L.R. et al. Separation and quantification of chemically diverse analytes in neutron irradiated fissile materials. J Radioanal Nucl Chem 282, 63–68 (2009). https://doi.org/10.1007/s10967-009-0263-8
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DOI: https://doi.org/10.1007/s10967-009-0263-8