Spent ion exchange resin-its treatment from the point of view of safe disposal.

Abstract

Ion exchange process is one of the treatment methods for radioactive waste. The resin becomes no longer useful after number of cycles of usage. At the same time the regenerated resin cannot be considered as non active waste for disposal. Hence it is felt necessary that the regenerated resin is treated in a fashion so as to result in a form which can be considered as inactive material. It is possible to convert this spent resin into multivalent ionic form which are generally non leachable, thus providing the necessary properties for meeting the disposal criteria. Studies were carried out for the exchange of radioactive ions on these resins with ions like Al3+, Sn4+, Pb2+ and Fe3+ etc. The studies included leachability aspects, exchange with other active ions, thermal characteristics, compressive strength of the cement blocks loaded with the resin etc. Our studies indicated that the order of the stability of the resin with respect to properties like leachability, exchange properties etc. follow the trend as follows: Sn4+ > Pb2+ > Al3+ > Fe3+.