2012•OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)Requires access
Simultaneous {sup 233}U and{sup 235}U characterization through the assay of delayed neutron temporal behavior
M. T. Sellers, E. C. Corcoran, D. G. Kelly
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Abstract
Aqueous solutions containing dissolved uranium-233 and uranium-235 were irradiated for 60's in the SLOWPOKE-2 reactor at the Royal Military College of Canada. The temporal behavior of the delayed neutrons produced was recorded by the Facility's Delayed Neutron Counting (DNC) system. The percentage of uranium-233 as a function of total fissile mass present in each sample ranged from 0 to 100% and was predicted by the DNC system with average absolute errors of {+-} 4%. Future work will upgrade the system electronics and software to reduce both uncertainties in timings and electrical noise. Mixture analysis will also be expanded to include plutonium-239 and fissile materials contained in non-aqueous matrices. (authors)