Reprocessing method of spent fuel
Description
Spent fuels are melted in molten chlorides, and then at least one of oxygen or a material releasing oxygen is supplied to the molten chlorides. Uranium (U), plutonium (Pu), neptunium (Np) and americium (Am) contained in the spent fuels are converted to insoluble oxides and precipitated. Then, U, Pu, Np and Am are separated from the molten chloride and recovered. In this case, the amount of precipitated insoluble oxides is detected by monitoring the amount of supplied oxygen and the change of the concentration of the dissolve oxygen ions. According to this method, a U/Pu mixture having a predetermined Pu/U ratio can be produced easily by controlling the amount of oxygen to be supplied, and can be recovered as a mixture not separated from each other. Accordingly, a mixture having U/Pu ratio suitable to MOX fuels can be provided by a convenient method at a low cost. (T.M.)
Availability note (English)
Available from JAPIO. Also available from EPO.Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- IPC:
- Int. Cl. G21C19/44; G21F9/06.
- IPC
- Int. Cl. G21C19/44; G21F9/06.
- Patent number
- JP patent document 9-80193/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28054589
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AMERICIUM; DISSOLUTION; MOLTEN SALTS; NEPTUNIUM; OXIDES; OXYGEN; PLUTONIUM; PRECIPITATION; REPROCESSING; SPENT FUELS; URANIUM
- Descriptors DEC
- ACTINIDES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NONMETALS; NUCLEAR FUELS; OXYGEN COMPOUNDS; REACTOR MATERIALS; SALTS; SEPARATION PROCESSES; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Secondary number(s)
- JP patent application 7-235265.