Retention of some hazardous radionuclides from nitric acid solution using tin(IV) antimonate as a cation exchanger

The removal of some hazardous radioactive nuclides such as Cs+, Co2+, Sr2and/or Eu3+ from radioactive liquid waste was carried out either by chemica l in-situ precipitation or by using a preformed precipitate of tin(TV) anti monate (SnSb). Stability of the product material for the chemical reagents was investigated at various concentrations of nitric and hydrochloric acids . Capacity and selectivity patterns for CS+, CO2+, Sr2+ and Eu3+ were deter mined on these matrices. Conditioning of the exhausted tin(IV) antimonate i n cement matrix was carried out with the study of some important parameters affecting the properties of the solidified waste forms such as, the compre ssive strength and the leaching coefficient of these nuclides from the soli dified waste form. The leaching coefficient of radioactive nuclides precipi tated in-situ with SnSb are smaller than those adsorbed on SnSb or plain or dinary portland cement.