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Abstract

A liquid containing radioactive ions is purified (decontaminated) by contacting the same with an inorganic ion exchange composition having ion exchange sites which can be occupied by the radioactive ions from the liquid. The ion exchange composition is a mixture of an ion exchange medium and an additive which is relatively inert to the ion exchange process and which is a sintering aid for the ion exchange medium designed to lower the sintering temperature of the ion exchange composition. The ion exchange composition may be disposed within a suitable container (e.g., cannister), e.g., made of 304L stainless steel or Inconel 601 and the ion exchange process may be carried out in such container. Alternatively, the ion exchange medium can be employed without being previously admixed with the additive. The additive, if desired, can be admixed at a later stage with the contaminated medium. Thereafter, the mixture may be sintered and disposed of in any desirable manner as by underground burial of the spent mixture within the container. Also, the container may be placed within a suitably designed furnace for carrying out the ion exchange process, sintering of the ion exchange composition and its safe disposal. Methods are also described for making a homogeneous mixture of the ion exchange medium and the additive which, for example, have a certain defined density and particle size relationship.

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