High-capacity annular centrifugal contactor

Journal Article · Sat Dec 01 04:00:00 EST 1973 · Nucl. Technol., v. 20, no. 3, pp. 200-202

OSTI ID:4409696

Bernstein, G J; Grosvenor, D E; Lenc, J F; Levitz, N M

A centrifugal contactor of unique design has been developed for solvent extraction processfng of high-plutonium-content fuels. The unit has a vertically suspended rotor that has a 4-in. inside dia and is 15 in. long (with a 12-in.- long separating zone). Aqueous and organic phases are fed into the annulus between the contactor casing and the spinning rotor and are mixed by skin friction. The mixture flows down the annulus and then up through an orifice in the bottom of the rotor. The phases are separated by centrifugal force as they flow up the inside of the rotor and are discharged at the top. Separating capacities (throughput) ranged from 4.5 gal/min at 2000 rpm to 15 gal/min at 3590 rpm. Essentially 100% stage efficiency was demonstrated in extraction and stripping of uranium between nitric acid and 30% tri-n-butyl phosphate in ndodecane diluent. The basic annular-mixer design is suitable for contactors with larger or smaller diameters. (auth)

• Research Organization: Argonne National Lab., IL
• NSA Number: NSA-29-002596
• OSTI ID: 4409696
• Journal Information: Nucl. Technol., v. 20, no. 3, pp. 200-202, Journal Name: Nucl. Technol., v. 20, no. 3, pp. 200-202; ISSN NUTYB
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*CENTRIFUGES-- PERFORMANCE TESTING
*SPENT FUELS-- REPROCESSING
EFFICIENCY
N40450 -- Chemistry--Radiochemistry & Nuclear Chemistry--Reactor Fuel Processing
N42200* --Engineering--Facilities & Equipment
NUCLEAR FUELS
OPERATION
PLUTONIUM
SEPARATION PROCESSES
SOLVENT EXTRACTION