No abstract

SuperLig / Resin / Cesium / Batch sorption / Isotherm / Distribution coefficientSummary. Batch ion exchange tests have been employed to evaluate the ability of SuperLig ® 644 resin to remove 137 Cs from highly alkaline nuclear waste solution. The batch sorption data indicated the SuperLig ® 644 resin has a relatively high sorption affinity for cesium with a predicted number of bed volumes required to reach 50% breakthrough in a column operation (generally known as λ value) of ∼ 400 based on an initial total cesium concentration of 12.1 µg/mL. The sorption data also obey the Freundlich and Dubinin-Radushkevich isotherms.

No abstract

No abstract

Five cycles of loading, elution, and regeneration were performed to remove technetium from a Hanford waste sample retrieved from Tank 241-AW-101 using SuperLig ® 639 resin. The waste sample was diluted to 4.95 M Na + and then was processed to remove 137 Cs through dual ion exchange columns each containing 15 mL of SuperLig ® 644. To remove 99 Tc, the cesium decontaminated solution was processed downwards through two ion exchange columns, each containing 12 mL of SuperLig ® 639 resin. The columns, designated as lead and lag, each had an inside diameter of 1.45 cm and a height of 30 cm. The columns were loaded in series, but were eluted and then regenerated separately. The average technetium loading for the cycles was 250 BV at 10% breakthrough. There was no significant difference in the loading performances among the five cycles. The percent removal of 99 Tc was > 99.94% and the average decontamination factor (DF) was ~ 1.7 x 10 3 . Approximately 99% of the 99 Tc loaded on the resin was eluted with < 15 BV of de-ionized water at 65 o C.