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, WA (United States)
- 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
Similar Records
Method for improving the extraction properties of a tributyl phosphate solution
PROPERTIES AND CLEANUP OF DEGRADED TRIBUTYL PHOSPHATE-AMSCO SOLUTIONS AND THE RELATIVE STABILITIES OF ALTERNATIVE EXTRACTANT-DILUENT SYSTEMS
COMPARISON OF DIALKYL PHENYLPHOSPHONATES WITH TRI-n-BUTYL PHOSPHATE IN NITRATE SYSTEMS: EXTRACTION PROPERTIES, STABILITY, AND EFFECT OF DILUENT ON THE RECOVERY OF URANIUM AND THORIUM FROM SPENT FUELS
Patent
·
Tue Mar 09 00:00:00 EST 1976
·
OSTI ID:862477
PROPERTIES AND CLEANUP OF DEGRADED TRIBUTYL PHOSPHATE-AMSCO SOLUTIONS AND THE RELATIVE STABILITIES OF ALTERNATIVE EXTRACTANT-DILUENT SYSTEMS
Technical Report
·
Wed Dec 11 00:00:00 EST 1963
·
OSTI ID:862477
COMPARISON OF DIALKYL PHENYLPHOSPHONATES WITH TRI-n-BUTYL PHOSPHATE IN NITRATE SYSTEMS: EXTRACTION PROPERTIES, STABILITY, AND EFFECT OF DILUENT ON THE RECOVERY OF URANIUM AND THORIUM FROM SPENT FUELS
Technical Report
·
Wed Jan 23 00:00:00 EST 1963
·
OSTI ID:862477
Related Subjects
method
improving
extraction
properties
tributyl
phosphate
solution
extractant
reprocessing
irradiated
nuclear
reactor
fuel
purex
process
containing
degradation
products
contacting
diazomethane
suitable
solvent
whereby
esterified
triester
phosphates
similar
purex process
tributyl phosphate
irradiated nuclear
suitable solvent
nuclear reactor
reactor fuel
degradation products
properties similar
extraction properties
phosphate extractant
phosphate solution
/999/423/976/987/
improving
extraction
properties
tributyl
phosphate
solution
extractant
reprocessing
irradiated
nuclear
reactor
fuel
purex
process
containing
degradation
products
contacting
diazomethane
suitable
solvent
whereby
esterified
triester
phosphates
similar
purex process
tributyl phosphate
irradiated nuclear
suitable solvent
nuclear reactor
reactor fuel
degradation products
properties similar
extraction properties
phosphate extractant
phosphate solution
/999/423/976/987/