Method for improving the extraction properties of a tributyl phosphate solution
Patent
·
OSTI ID:862477
- Richland, WA
- Kennewick, WA
A method for improving the extraction properties of a tributyl phosphate extractant used for reprocessing irradiated nuclear reactor fuel (Purex Process) containing degradation products of tributyl phosphate by contacting the extractant with diazomethane in a suitable solvent whereby the degradation products are esterified to triester phosphates which have extraction properties similar to those of tributyl phosphate.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- DOE Contract Number:
- AT(45-1)-1830
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- Patent Number(s):
- US 3943204
- OSTI ID:
- 862477
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
/999/423/976/987/
contacting
containing
degradation
degradation products
diazomethane
esterified
extractant
extraction
extraction properties
fuel
improving
irradiated
irradiated nuclear
method
nuclear
nuclear reactor
phosphate
phosphate extractant
phosphate solution
phosphates
process
products
properties
properties similar
purex
purex process
reactor
reactor fuel
reprocessing
similar
solution
solvent
suitable
suitable solvent
tributyl
tributyl phosphate
triester
whereby
contacting
containing
degradation
degradation products
diazomethane
esterified
extractant
extraction
extraction properties
fuel
improving
irradiated
irradiated nuclear
method
nuclear
nuclear reactor
phosphate
phosphate extractant
phosphate solution
phosphates
process
products
properties
properties similar
purex
purex process
reactor
reactor fuel
reprocessing
similar
solution
solvent
suitable
suitable solvent
tributyl
tributyl phosphate
triester
whereby