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Method for cleaning solution used in nuclear fuel reprocessing

Patent ·
OSTI ID:6613245
; ;

Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-nbutyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.

Assignee:
Dept. of Energy
Patent Number(s):
US 4358426
OSTI ID:
6613245
Country of Publication:
United States
Language:
English

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Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPLEXES
AQUEOUS SOLUTIONS
CHALCOGENIDES
CLEANING
COMPLEXES
DISPERSIONS
ENERGY SOURCES
FUELS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
MATERIALS
MIXTURES
NITRIC ACID
NITROGEN COMPOUNDS
NITROGEN OXIDES
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PHOSPHATES
PHOSPHORUS COMPOUNDS
PLUTONIUM COMPLEXES
REACTOR MATERIALS
REMOVAL
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SPENT FUELS
TRANSITION ELEMENT COMPLEXES
TRANSURANIUM COMPLEXES
URANIUM COMPLEXES
ZIRCONIUM COMPLEXES