Separation of uranium from technetium in recovery of spent nuclear fuel

Patent · Sat Dec 31 23:00:00 EST 1983

OSTI ID:864964

Pruett, David J ^[1]; McTaggart, Donald R ^[1]

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1. Knoxville, TN

Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc.sup.+7 therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
• DOE Contract Number: W-7405-ENG-26
• Assignee: United States of America as represented by United States (Washington, DC)
• Patent Number(s): US 4443413
• OSTI ID: 864964
• Country of Publication: United States
• Language: English

Related Subjects

/423/
aqueous
aqueous stream
contacting
containing
diluent
extract
fuel
hydrazine
nuclear
nuclear fuel
organic
organic phase
phase
phase containing
phosphate
process
product
product stream
purex
purex process
recovery
reduce
reduced
separated
separation
species
spent
spent nuclear
stream
tc
technetium
therein
tributyl
tributyl phosphate
uranium