Radionuclide CHaracterization of Spent Purification Filters

Abstract

A remote handling facility is described which will aid in the assessment of the radionuclide m1x and total activity content of spent purification filters. The facility will also dry filters as part of their preparation for off-site shipment. One possible system design, consisting of a robot w1th five degrees of freedom, a shielded Ge-Li detector, and a vacuum drying system, is described. Benefits could include reduced operating and waste storage or burial


costs, feedback on filter performance, and an improved understanding of environmental protection requirements.