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Title: Method for cleaning solution used in nuclear fuel reprocessing

Abstract

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.

Inventors:
; ;
Issue Date:
OSTI Identifier:
6053085
Assignee:
Dept. of Energy TIC; ERA-06-034357; EDB-81-114912
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; CARBOXYLIC ACID ESTERS; CHEMICAL REACTIONS; DBP; REMOVAL; HYDRAZINE; OXALIC ACID ESTERS; PLUTONIUM COMPLEXES; PROCESS SOLUTIONS; CLEANING; TARTARIC ACID ESTERS; URANIUM COMPLEXES; ZIRCONIUM COMPLEXES; COMPARATIVE EVALUATIONS; DODECANE; EXPERIMENTAL DATA; NITRIC ACID; ORGANIC SOLVENTS; PH VALUE; REPROCESSING; SPENT FUELS; TBP; ACTINIDE COMPLEXES; ALKANES; BUTYL PHOSPHATES; COMPLEXES; DATA; DISPERSIONS; ENERGY SOURCES; ESTERS; FUELS; HYDROCARBONS; HYDROGEN COMPOUNDS; INFORMATION; INORGANIC ACIDS; MATERIALS; MIXTURES; NITROGEN COMPOUNDS; NUCLEAR FUELS; NUMERICAL DATA; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; PHOSPHORIC ACID ESTERS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLUTIONS; SOLVENTS; TRANSITION ELEMENT COMPLEXES; TRANSURANIUM COMPLEXES; 050800* - Nuclear Fuels- Spent Fuels Reprocessing; 400105 - Separation Procedures

Citation Formats

Tallent, O.K., Crouse, D.J., and Mailen, J.C. Method for cleaning solution used in nuclear fuel reprocessing. United States: N. p., 1980. Web.
Tallent, O.K., Crouse, D.J., & Mailen, J.C. Method for cleaning solution used in nuclear fuel reprocessing. United States.
Tallent, O.K., Crouse, D.J., and Mailen, J.C. Wed . "Method for cleaning solution used in nuclear fuel reprocessing". United States.
@article{osti_6053085,
title = {Method for cleaning solution used in nuclear fuel reprocessing},
author = {Tallent, O.K. and Crouse, D.J. and Mailen, J.C.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {12}
}