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Method for cleaning solution used in nuclear fuel reprocessing

Patent ·
OSTI ID:864390
 [1];  [1];  [1]
  1. Oak Ridge, TN
+ Show Author Affiliations
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.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
Assignee:
United States of America as represented by United States (Washington, DC)
Patent Number(s):
US 4358426
OSTI ID:
864390
Country of Publication:
United States
Language:
English

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Related Subjects

/423/976/
acid
aforesaid
aqueous
aqueous solution
carboxylic acid
cleaning
cleaning solution
complex
consisting
contacted
degradation
di-n-butyl
dicarboxylic
dicarboxylic acid
dodecane
formed
fuel
fuel processing
fuel reprocessing
hydrazine
hydroxycarboxylic
method
nuclear
nuclear fuel
phosphate
plutonium
processing
processing solution
product
removing
reprocessing
salt
salt form
solution
solution consisting
solvent
therein
tri-n-butyl
tri-n-butyl phosphate
uranium
zirconium