Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 123 / Number 1 / Pages 60-66
Thomas N. Sargent, Jr., Thomas J. Overcamp, Dennis F. Bickford, Connie A. Cicero-Herman
Nuclear Technology / Volume 123 / Number 1 / Pages 60-66
Format:electronic copy (download)
Tests were conducted using a stirred-tank melter to vitrify nonradioactive, cesium-laden organic ion-exchange resin. This resin, which is highly effective in removing cesium from solution, was developed to replace the complex sodium tetraphenylborate precipitation process used at the Defense Waste Processing Facility at the Savannah River Site to remove 137Cs from a wastewater solution. The glass produced had a Fe2+/FeTotal ratio that was acceptable for high-level waste glass. No damage to the melter was observed. Lower-bound estimates of overall cesium retention in the glass range from 70.5 to 73.9%. Only 2.1 to 4.3% of the cesium was emitted from the melter. Because between 21.8 and 27.4% of the cesium was not recovered, the overall cesium retention may have been substantially higher.
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