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In this project faculty and students will investigate the potential to use combined neutron and gamma-ray detector systems to measure quantities and isotopic constituents contained during separations and intermediate storage. This will require knowledge of the nuclear and decay characteristics of materials during processing, the development of conceptual designs of monitoring systems, radiation transport studies to develop an understanding of operational regimes, and experiments to confirm performance. The project will begin with a literature search, compilation of characteristics of separations systems under development in the AFCI program, as well as a compilation of known data about nuclear characteristics (gamma-ray and neutron cross sections, neutron multiplicity, and spontaneous fission) of individual isotopes of the higher actinides. AFCI Separations staff members will provide information about processing equipment and process chemistry (constituents of solutions). This information will then be used in radiation transport and scoping studies to develop concepts for combined gamma-ray, neutron, and active and passive detection techniques. In subsequent years experiments will be conducted at UNLV and/or the Idaho State University, where an electron linac at the Idaho Accelerator Center (IAC) will be used to induce radioactivity and/or fission in process streams or containers.


Actinide elements – Separation; Radioactive wastes — Purification; Reactor fuel reprocessing; Spent reactor fuels





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Nuclear Commons