Technetium-99 in SRP high-level waste and saltstone.

摘要

Analyses of sludge and soluble waste samples and the inventory of sludge and soluble waste have been used to estimate the concentration of technetium-99 (Tc-99) in sludge solids and soluble waste. These data were also used to establish if the source term assumptions for Tc-99 in the Defense waste Processing Facility (DWPF) flowsheet are accurate and determine the fraction of the Tc-99 inventory in the waste that is soluble. This analysis was needed to establish if the present basis for decontaminated salt feed to the saltstone process is correct. These results and the projected leach rate for Tc-99 from saltstone can then be used to establish if Tc-99 must be removed from contaminated supernate.