Removal of Cesium From Acidic Radioactive Tank Waste Using IONSIV IE-911 (CST)
IONSIV IE-911, or the engineered form of crystalline silicotitanate (CST), manufactured by UOP Molecular Sieves, has been evaluated for the removal of cesium from Idaho National Engineering and Environmental Laboratory (INEEL) acidic radioactive tank waste. A series of batch contacts and column tests were performed by using three separate batches of CST. Batch contacts were performed to evaluate the concentration effects of nitric acid, sodium, and potassium ions on cesium sorption. Additional batch tests were performed to determine if americium, mercury, and plutonium would sorb onto IONSIV IE-911. An equilibrium isotherm was generated by using a concentrated tank waste simulant. Column tests using a 1.5 cm 3 column and flow rates of 3, 5, 10, 20, and 30 bed volumes (BV)/hr were performed to elucidate dynamic cesium sorption capacities and sorption kinetics. Additional experiments investigated the effect of CST batch and pretreatment on cesium sorption. The thermal stability of IONSIV IE-911 was evaluated by performing thermal gravimetric analysis/differential thermal analysis. Overall, IONSIV IE-911 was shown to be effective for cesium sorption from complex, highly acidic solutions; however, sorbent stability in these solutions may have a deleterious effect on cesium sorption.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911976
- Report Number(s):
- INEEL/JOU-02-01452; SSTEDS; TRN: US0800251
- Journal Information:
- Separation Science and Technology, Vol. 39, Issue 10; ISSN 0149-6395
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AMERICIUM
CESIUM
FLOW RATE
ISOTHERMS
KINETICS
MERCURY
MOLECULAR SIEVES
NITRIC ACID
PLUTONIUM
POTASSIUM IONS
SODIUM
SORPTION
STABILITY
TANKS
THERMAL ANALYSIS
WASTES
Cesium sorption
Ion-exchange material
Radioactive tank waste
Thermal stability