Re-processing method for spent nuclear fuel
Description
Purpose: To re-process spent oxide or mixed oxide fuels at a reduced cost while decreasing the amount of secondary radioactive wastes generated. Method: Oxide fuels, etc. to be re-processed are once converted into chlorides so that simple electrolytic refining method can be applied. Then, deposition products are again converted into oxides and regenerated as fuels. This method can simplify the re-processing step as compared with the conventional Purex process and can reduce the cost. In addition, conversion into chlorides can eliminate the requirement of using organic solvents which are degraded remarkably with radioactive rays as in the Purex process and can conduct re-processing while reducing the amount of the secondary radioactive wastes generated. (Takahashi, M.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- IPC:
- Int. Cl. G21C19/46.
- IPC
- Int. Cl. G21C19/46.
- Patent number
- JP patent document 63-171397/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20018039
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CHLORIDES; CHLORINATION; ELECTROREFINING; PLUTONIUM OXIDES; REPROCESSING; SPENT FUELS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; CHLORINE COMPOUNDS; ELECTROLYSIS; ENERGY SOURCES; FUELS; HALIDES; HALOGEN COMPOUNDS; HALOGENATION; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR MATERIALS; REFINING; SEPARATION PROCESSES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Secondary number(s)
- JP patent application 62-1791.