Coprocessing solvent extraction studies

Journal Article · Sun Apr 01 04:00:00 EST 1979 · Nucl. Technol.; (United States)

OSTI ID:5780482

Okamoto, M S; Thompson, M C

A coprocessing solvent extraction flowsheet for recovery and purification of light water reactor (LWR) fuels has been developed. This flowsheet never completely separates uranium from plutonium. The flowsheet has changed operation of the partitioning contactor to achieve partial partitioning of uranium and plutonium. Partial partitioning has been demonstrated with simulated feeds and irradiated LWR fuel solutions with hydroxylamine nitrate reductant to concentrate the plutonium by factors of 6 to 27.4. Nitrite was shown to interfere with the reduction of plutonium. Increased hydroxylamine concentrations gave normal reduction behavior. 7 figures, 5 tables.

• Research Organization: E.I. du Pont de Nemours and Co., Aiken, SC
• OSTI ID: 5780482
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 43:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
AMINES
CHEMICAL REACTIONS
DATA
DATA FORMS
DIAGRAMS
ELEMENTS
ENERGY SOURCES
EXPERIMENTAL DATA
EXTRACTION
FLOWSHEETS
FUELS
HYDROXYLAMINE
INFORMATION
INTERFERENCE
ISOLATED VALUES
METALS
NITRITES
NITROGEN COMPOUNDS
NUCLEAR FUELS
NUMERICAL DATA
ORGANIC COMPOUNDS
PLUTONIUM
REACTOR MATERIALS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPENT FUELS
TRANSURANIUM ELEMENTS
URANIUM
WATER COOLED REACTORS