Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Crystalline silicotitanates--new ion exchanger for selective removal of cesium and strontium from radwastes

Technical Report ·
DOI:https://doi.org/10.2172/369706· OSTI ID:369706
; ; ;  [1];  [2]
  1. Sandia National Laboratories, Albuquerque, NM (United States)
  2. Texas A&M Univ., College Station, TX (United States)

A new class of inorganic ion exchange material called crystalline silicotitanates (CST) has been developed for radioactive waste treatment in a collaborative effort between Sandia National Laboratories and Texas A&M University. The Sandia National Laboratories Laboratory Directed Research and Development program provided the initial funding for this effort and this report summarizes the rapid progress that was achieved. A wide range of compositions were synthesized, evaluated for cesium (Cs) removal efficiency, and a composition called TAM-5 was developed that exhibits high selectivity and affinity for Cs and strontium (Sr). Tests show it can remove parts per million concentrations of Cs{sup +} from highly alkaline, high-sodium, simulated radioactive waste solutions modeled after those at Hanford, Oak Ridge, and Savannah River. In experiments with solutions that simulate highly alkaline Hanford defense wastes, the crystalline silicotitanates exhibit distribution coefficients for Cs{sup +} of greater than 2,000 ml/g, and distribution coefficients greater than 10,000 ml/g for solutions adjusted to a pH between 1 and 10. In addition, the CSTs were found to exhibit distribution coefficients for Sr{sup +} greater than 100,000 ml/g and for plutonium of 2,000 ml/g from simulated Hanford waste. The CST crystal structure was determined and positions of individual atoms identified using x-ray and neutron diffraction. The structural information has permitted identification of the ion exchange sites and provided insights into the strong effect of pH on Cs ion exchange. Information on the synthesis, composition, and structure of CST is considered proprietary and is not discussed in this report.

Research Organization:
Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC04-94AL85000
OSTI ID:
369706
Report Number(s):
SAND--96-1929; ON: DE96014763
Country of Publication:
United States
Language:
English

Similar Records

Treatment of liquid nuclear wastes with advanced forms of titanate ion exchangers
Conference · Sun Feb 28 23:00:00 EST 1993 · OSTI ID:10142196

Treatment of liquid nuclear wastes with advanced forms of titanate ion exchangers
Conference · Thu Dec 31 23:00:00 EST 1992 · OSTI ID:6637865

Use of silicotitanates for removing cesium and strontium from defense waste
Journal Article · Mon Oct 31 23:00:00 EST 1994 · Industrial and Engineering Chemistry Research; (United States) · OSTI ID:6699787