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Abstract  

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.

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Journal of Radioanalytical and Nuclear Chemistry
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

Summary  

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.

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