Published April 8, 1991 | Version v1
Patent Metadata-only

Method of reprocessing spent fuels by low temperature/high load purex processing

Creators

Description

In the present invention, the temperature of an extraction system is lowered to 0 to 5degC to increase uranium concentration in an organic solvent in order to separate uranium and plutonium from each other. With this constitution, both elements are separated easily without adjustment and control for atomic valence by utilizing the effect of decreasing the extraction distribution ratio for plutonium while increasing the distribution ratio for uranium. Accordingly, troubles due to an erroneous operation can be decreased and actinide elements such as uranium, plutonium and neptunium can be separated and recovered easily and safely. (T.M.)

Availability note (English)

Available from JAPIO. Also available from INPADOC.

Additional details

Publishing Information

Imprint Pagination
6 p.
IPC:
Int. Cl. G21C19/46.
IPC
Int. Cl. G21C19/46.
Patent number
JP patent document 3-82997/A/

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
22088406
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
NEPTUNIUM; PARTITION; PLUTONIUM; PUREX PROCESS; QUANTITY RATIO; SOLVENT EXTRACTION; SPENT FUELS; TBP; TEMPERATURE DEPENDENCE; URANIUM
Descriptors DEC
ACTINIDES; BUTYL PHOSPHATES; ELEMENTS; ENERGY SOURCES; ESTERS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; PHOSPHORIC ACID ESTERS; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS

Optional Information

Secondary number(s)
JP patent application 1-218880.