Radioactive waste immobilization using ion-exchange...

Details Radioactive waste immobilization using ion-exchange... Radioactive waste immobilization using ion-exchange...

C - Chemistry, Metallurgy

03

C

261/14, 403/2, 3

C03C 10/00 (2006.01) G21F 9/12 (2006.01) G21F 9/16 (2006.01) G21F 9/30 (2006.01)

Patent

CA 1199043

ABSTRACT A process for producing a stable glass-ceramic product useful for storing radioactive nuclear waste products for extraordinarily long periods of time without danger to the environment, in which liquid wastes having high level radioactivity are passed through an ion exchange medium, such as a titanate to deposit the highly radioactive materials thereon and produce a low level radioactive liquid waste which can be safely disposed of in a less rigorous manner than high level wastes is described. The ion exchange medium carrying the highly radioactive materials is heated, with any additional glass forming materials which may be necessary, to form a melt having a composition in the range: Image where M is selected from Na, K; M1 is selected from Ca, Ba, Sr; M11 is selected from Al, B, Fe, Cr; M111 is selected from Zr, Sn, Zn and M1V is selected from P, Ta, Nb. This glassy composition is cooled and then reheated to a selected temperature, dependent on the composition, in the range 950°C - 1050°C to effect devitrification into a glass-ceramic product comprising crystalline sphene in a glassy matrix. Preferably most of the radioactive material will report in the crystalline sphene phase.

415622

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