scholarly journals Crystalline Silicotitanate (CST) Ion Exchange Media Performance Evaluations in SRS Average Supernate Simulant and Tank 10H Waste Solution to Support TCCR

2018 ◽  
Author(s):  
William D. King ◽  
Larry L. Hamm ◽  
Charles J. Coleman ◽  
Fernando F. Fondeur ◽  
Scott H. Reboul
2021 ◽  
Author(s):  
Sandra Fiskum ◽  
Amy Westesen ◽  
Andrew Carney ◽  
Truc LT Trang-Le ◽  
Reid Peterson

2020 ◽  
Vol 39 (1) ◽  
pp. 90-103
Author(s):  
Emily L. Campbell ◽  
Sandra K. Fiskum ◽  
Truc T. Trang-Le ◽  
Reid A. Peterson

2006 ◽  
Vol 94 (12) ◽  
Author(s):  
K. V. Chetty ◽  
R. Swarup ◽  
V. Venugopal ◽  
P. R. Vasudeva Rao

Removal of radioactive nuclides from effluents is important for the safe disposal of the radioactive waste. In the present work ion exchange studies were carried out using simulated alpha active organic liquid scintillator and ethyl alcohol waste solutions containing Pu and Am using different resins. The time of equilibration and batch data were obtained under different conditions for individual resins as well as their mixtures. The indigenously developed Macroporous bifunctional phosphinic acid (MPBPA) resin was found to be suitable for the removal of alpha activity mainly due to Pu and Amberlite IR-120 and Biorad 50W × 8 for removal of Am. The results indicated that the presence of alcohol in the scintillator solution helps in increasing the distribution ratio. Experiments were carried out with column containing either MPBPA resin alone or with additional resin bed of Amberlite IR-120 using active organic liquid scintillator waste (with and without dilution with alcohol). Studies were also carried out on alcoholic waste generated in the laboratory during the washing of the used liquid scintillator vials. The alcohol after removal of activity either could be reused or could be disposed off directly as a ‘potentially’ active waste.


2005 ◽  
Vol 93 (8) ◽  
Author(s):  
Kofi Adu-Wusu ◽  
Neguib M. Hassan ◽  
Charles A. Nash ◽  
James C. Marra

SummaryBatch ion exchange tests have been employed to evaluate the ability of SuperLig® 644 resin to remove


1999 ◽  
Vol 556 ◽  
Author(s):  
M. Nyman ◽  
T. M. Nenoff ◽  
Y. Su ◽  
M. L. Balmer ◽  
A. Navrotsky ◽  
...  

AbstractThe radioactivity of the Hanford site waste tanks is primarily from 137Cs and 90Sr, of which can both be selectively removed from solution using a crystalline silicotitanate (CST) ion exchanger. We are currently seeking waste forms alternative to borosilicate glass for Cs-CSTs. In order to obtain a fundamental basis for the development of an alternative waste form, we are investigating synthesis and characterization of CST component phases, namely Cs-Si-Ti-O phases. Two novel Cs-Ti-Si-O phases (one porous, one condensed) have been hydrothermally synthesized, characterized and evaluated as waste form candidates based on chemical and thermal stability, leachability, and ion exchange capabilities.


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