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Treatment of liquid nuclear wastes with advanced forms of titanate ion exchangers

A new class of inorganic ion exchange materials that can separate low parts per million level concentrations of Cs[sup +] from molar concentrations of Na[sup +] has recently been developed as a result of a collaborative effort between Sandia National Laboratories and Texas A M University. The materials, called crystalline silicotitanates, show significant potential for application to the treatment of aqueous nuclear waste solutions, especially neutralized defense wastes that contain molar concentrations of Na[sup +] in highly alkaline solutions. In experiments with alkaline solutions that simulate defense waste compositions, the crystalline silicotitanates exhibit distribution coefficients for Cs[sup +] of greater than 2,000 ml/g, and distribution coefficients greater than 10,000 for solutions adjusted to a pH between 1 and 10. Additionally, the crystalline silicotitanates were found to exhibit distribution coefficients for Pu and Sr[sup 2+] of greater than 2,000 and 100,000 respectively. Development of these materials for use in processes to treat defense waste streams is currently being pursued.