RECOVERY OF NEPTUNIUM-237 FROM PROCESS RESIDUES BY SOLVENT EXTRACTION

Journal Article · Wed Dec 31 23:00:00 EST 1958 · Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol.

DOI:https://doi.org/10.1021/ie50589a036· OSTI ID:4261085

Flanary, J R; goode, J H

A solvent extraction process, utilizing tributyl phosphate as the extractant, was developed and proved on a semiworks scale for the separation of neptunium from processing residues. This extends the usefulness of tributyl phosphate as a solvent for the recovery of the heawy elements, adding neptunium to thorium, uranium, and plutonium. Standard laboratory techniques of batch equilibrations and batch countercurrent experiment8, using tracer techniques, established optimum conditions for primary extraction of uranium and neptunium and their separation. Results of these tests were confirmed in a putsed column demonstration. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• Sponsoring Organization: USDOE
• NSA Number: NSA-13-004493
• OSTI ID: 4261085
• Journal Information: Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol., Journal Name: Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol. Vol. Vol: 51; ISSN IECHA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BUTYL PHOSPHATES
CHEMISTRY
COUNTER CURRENT
EXTRACTION COLUMNS
NEPTUNIUM 237
NEPTUNIUM COMPOUNDS
PLUTONIUM COMPOUNDS
PULSE COLUMNS
PULSES
RADIOCHEMISTRY
RECOVERY
RESIDUES
SEPARATION PROCESSES
SOLVENT EXTRACTION
TESTING
THORIUM COMPOUNDS
TRACER TECHNIQUES
URANIUM COMPOUNDS
WASTE PROCESSING