The results of our studies on the properties of hydrous titanium (IV) -silicon oxides (TS) and hydrous titanium (IV) -zirconium oxides (TZ) as solidification media of liquid radioactive wastes have been reviewed. TS exchangers with 37 to 67 mol% Ti have much larger cation-exchange capacity than the component simple hydrous metal oxides, while the cation-exchange capacity of TZ increases linearly with titanium content in the exchangers. Though the affinity of these exchangers for representative metal ions increases with the acidity of the exchange sites, no such simple relation holds for transition metal ions; in the sorption of transition metal ions, the formation of a covalent bond is a key factor in determining the selectivity of the exchangers, along with the remote coulombic interaction.These exchangers do not suffer from any drastic change in the crystallinity upon heating up to 600 °C, and are much more heat-resistant than simple hydrous metal oxides.The dissolutions of Sr
2+, Co
2+, Eu
3+and Th
4+ from the exchangers calcined at ≥ 900°C are very slow due to the crystallization of strontium titanium silicate or titanates of Co
2+, Eu
3+ and Th
4+ ions. The leaching rates of Cs
+ and UO
22+ from TS significantly decrease with increasing temperature for thermal treatment, while such effect is not observed in TZ due to the formation of soluble Cs
2O and α -U
3O
8. In calcined TScontaining Cs
+ and UO
22+, most of the intense X-ray diffraction peaks cannot be assigned to known compounds, indicating the formation of crystallographically unknown hardly soluble caesium titanium silicate and uranium titanium silicate. Based on these results, we can conclude that TS is a promising material for the solidification of radwaste.
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