Synthetic Na/K-birnessite for efficient management of Sr(II) from nuclear waste

The efficient separation for alternate use and management of Sr-90 in nuclear waste is an important research activity in nuclear power industries. Herein we have demonstrated an efficient separation of Sr2+ by birnessite type sodium and potassium phyllomanganates (AxMn(2)O(4)-yH(2)O; A = Na+ and K+). Both the materials were prepared by oxidation of Mn(OH)(2) by flowing oxygen atmosphere in presence of large excess of alkali hydroxide. Mn(OH)(2) was prepared by precipitation method using solutions of MnCl2 and NaOH or KOH. The XRD studies revealed that both materials have layered monoclinic (C2/m) structures made of sheets of edge shared MnO6 octahedra. The Na+ or K+ ions were located in between these layers and provide charge neutrality to the structure. From thermogravimetric and XRD studies, the compositions of the prepared phyllomanganates are found to be Na(0.5)Mn(2)O(4-)0.96H(2)O (NMO) and K(0.5)Mn(2)O(4-)0.6H(2)O (KMO). The ion exchange studies carried out using radioactive Sr-85(2+) solutions revealed large distribution constant (K-d) in a wider range of pH (2 to 14). Maximum K-d (27,000 mL/g) for NMO is observed in neutral medium which decreased to similar to 19,000 mL/g at pH 14, while the K-d (similar to 22,000 mL/g) of KMO is relatively insensitive to pH. Higher preference of Sr2+ ions over Na+ and K+ have been concluded from the kinetics of exchange process. Ion exchange capacities of NMO and KMO are: 9.64 mmol/g and 1.09 mmol/g, respectively. Interference studies with several commonly present ions in nuclear waste like Al3+, Ca2+, H+ and Na+ ions, indicated appreciable interference only from Al3+.