Method for improving the extraction properties of a tributyl phosphate solution

Patent · Mon Mar 08 23:00:00 EST 1976

OSTI ID:7186507

Martin, E C; Bruns, L E

A method is given 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. The extractant is contacted 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.

• Assignee: Energy Research and Development Administration
• Patent Number(s): US 3943204
• OSTI ID: 7186507
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
400600 -- Radiation Chemistry
BUTYL PHOSPHATES
DIAZO COMPOUNDS
ESTERS
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC SOLVENTS
PHOSPHORIC ACID ESTERS
PUREX PROCESS
REPROCESSING
SEPARATION PROCESSES
SOLVENT PROPERTIES
SOLVENTS
TBP