Method for cleaning solution used in nuclear fuel reprocessing

Patent · Tue Dec 16 23:00:00 EST 1980

OSTI ID:6053085

Tallent, O K; Crouse, D J; Mailen, J C

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-n-butyl 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.

• DOE Contract Number: W-7405-ENG-26
• Assignee: Dept. of Energy
• Patent Number(s): None
• OSTI ID: 6053085
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDE COMPLEXES
ALKANES
BUTYL PHOSPHATES
CARBOXYLIC ACID ESTERS
CHEMICAL REACTIONS
CLEANING
COMPARATIVE EVALUATIONS
COMPLEXES
DATA
DBP
DISPERSIONS
DODECANE
ENERGY SOURCES
ESTERS
EXPERIMENTAL DATA
FUELS
HYDRAZINE
HYDROCARBONS
HYDROGEN COMPOUNDS
INFORMATION
INORGANIC ACIDS
MATERIALS
MIXTURES
NITRIC ACID
NITROGEN COMPOUNDS
NUCLEAR FUELS
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC SOLVENTS
OXALIC ACID ESTERS
PH VALUE
PHOSPHORIC ACID ESTERS
PLUTONIUM COMPLEXES
PROCESS SOLUTIONS
REACTOR MATERIALS
REMOVAL
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SOLVENTS
SPENT FUELS
TARTARIC ACID ESTERS
TBP
TRANSITION ELEMENT COMPLEXES
TRANSURANIUM COMPLEXES
URANIUM COMPLEXES
ZIRCONIUM COMPLEXES