RECOVERY OF U - PU IN RADIOACTIVE WASTE BY INCINERATION TO MOLTEN SULPHATES AND ELECTROLYSIS
The process of recuperation of alpha waste consists of putting the waste into solution by pyrolysis in a bath of sulphates melted at about 600 degrees C then, in the same bath, to recuperate the alpha elements by electrolysis. It is here applied essentially to uranium. The principal results show that, with the reservation of operating with concentrated baths, among which are the "real" pyrolysats of Agip, one can obtain deposits of uranium of good quality (composition varying from U-4O-8 to UO-2 in the course of electrolysis). They are thick (several mm) and well crystallized capable of extraction yields of 95 to 99% (however the electric output is weakened by the presence of ashes). Electrolysis appears therefore to be an efficacious process of recuperation of uranium (study completed by polarization curves and corrosion tests). The purpose of these results is to check on waste containing plutonium.
Bibliographic Reference: EUR 9486 FR (1984) FS, 71 P., BFR 250, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989125037300 / Last updated on: 1987-04-01
Available languages: fr