Published March 28, 1997 | Version v1
Patent

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.