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/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 25027584
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ELECTROLYSIS; MAGNESIUM; MELTING; REPROCESSING; SEPARATION PROCESSES; SPENT FUELS; STORAGE FACILITIES; TRANSURANIUM ELEMENTS; URANIUM; URANIUM OXIDES; VOLUME
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALKALINE EARTH METALS; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTOR MATERIALS; URANIUM COMPOUNDS
Optional Information
- Secondary number(s)
- JP patent application 4-5048.