The Savannah River Site (SRS) Burial Ground had a container labeled as Box 33 for which they had no reliable solid waste stream designation. The container consisted of an outer box of dimensions 48″ × 46″×66″
and an inner box that contained high density and high radiation dose material. From the outer box Radiation Control measured
an extremity dose rate of 22 mrem/h. With the lid removed from the outer box, the maximum dose rate measured from the inner
box was 100 mrem/h extremity and 80 mrem/h whole body. From the outer box the material was sufficiently high in density that
the Solid Waste Management operators were unable to obtain a Co-60 radiograph of the contents. Solid Waste Management requested
that the Analytical Development Section of Savannah River National Laboratory perform a γ-ray assay of the item to evaluate
the radioactive content and possibly to designate a solid waste stream. This paper contains the results of three models used
to analyze the measured γ-ray data acquired in an unusual configuration.