We have successfully incorporated high surface area particles of titanate ion-exchange materials (monosodium titanate and
crystalline silicotitanate) into porous and inert support membrane fibrils. The resulting membrane sheets were used to evaluate
the removal of surrogate radioactive materials for cesium-137 and strontium-90 from high caustic nuclear waste simulants.
The membrane supports met the nominal requirement for non-chemical interaction with the embedded ion-exchange materials and
were porous enough to allow sufficient liquid flow. Most of the stamped out 47-mm size titanium impregnated ion-exchange membrane
discs removed more than 96% of dissolved cesium-133 and strontium-88 from caustic nuclear waste salt simulants.
Authors:T. L. White, T. L. White, K. B. Martin, K. B. Martin, L. N. Oji, L. N. Oji, D. P. DiPrete, D. P. DiPrete, and W. R. Wilmarth
One waste remediation process used at the Savannah River Site was the in-tank precipitation of the beta-emitting 137Cs from high-level waste (HLW) using sodium tetraphenylborate (NaTPB) followed by processing the resulting decontaminated
filtrate into grout at the Saltstone Production Facility (SPF). A simple method was developed for the monitoring of tetraphenylborate
(TPB) in high-level waste (HLW) containing up to 0.38 Ci/gal of 137Cs. Separation was achieved by extraction of the high sodium-bearing waste with acetonitrile followed by analysis using reversed-phase
high performance liquid chromatography (HPLC). The sample preparation method allowed for the handling of an organic extraction
layer that had 94% less acitivity than the HLW sample. The subsequent HPLC analysis of the extraction layer determined the
TPB concentration in HLW waste to 0.8 mg/l with a %rsd of 8.