Published July 30, 1993 | Version v1
Patent

Separation and recovery method for depleted uranium from spent fuel

Description

Spent oxide fuels are reduced in a molten salt of CaCl2-CaF2 to convert them into metals, then melted in an Fe-U bath disposed in an electrolytic refining vessel and brought into contact with molten Mg, to extract transuranium elements and rare earth elements contained in the Fe-U bath as metals in the molten Mg. Then molten Mg is removed and the residue is brought into contact with KCl-LiCl molten salt and electrolyzed using the Fe-U as an anode. Then, uranium is recovered by deposition on an iron cathode disposed in chloride electrolytes of the electrolytic refining vessel. Uranium and transuranium elements can be thus separated and, for example, depleted uranium for use in blanket fuels can be recovered easily. This can greatly reduce the temporary storage amount of depleted uranium, to eliminate requirement for a large-scaled facility used exclusively for storing uranium and long time management for uranium. (T.M.)

Availability note (English)

Available from JAPIO. Also available from EPO.

Additional details

Publishing Information

Imprint Pagination
5 p.
IPC:
Int. Cl. G21C19/44.
IPC
Int. Cl. G21C19/44.
Patent number
JP patent document 5-188186/A/

Optional Information

Secondary number(s)
JP patent application 4-5048.