Process to improve the removal of suspended solids in leached uranium ore clarification

Patent · Tue Nov 10 00:00:00 EST 1987

OSTI ID:5862745

Mc Curdy, J W; Danyliw, B H

A process to improve suspended solids removal from leached uranium ore by filtration on a filter cloth is described comprising (a) contacting, prior to contact with the leached uranium ore, the filter cloth with an effective amount of a polymer selected from the group consisting of homopolymers of acrylamide having a molecular weight of 3,000,000 to 8,000,000 and copolymers of acrylamide and dimethyl diallyl ammonium chloride having a molecular weight of 1,000,000 to 8,000,000, containing at least 50% acrylamide and less than 50% dimethyl diallyl ammonium chloride, by weight; and (b) passing the leached uranium ore through the filter cloth, wherein the leached uranium ore contains an effective amount of an acrylamide polymer as a filtration aid.

• Assignee: Calgon Corp., Pittsburgh, PA
• Patent Number(s): US 4705672
• OSTI ID: 5862745
• Resource Relation: Patent File Date: Filed date 28 Apr 1986
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
URANIUM ORES
FILTRATION
LEACHING
ACRYLAMIDE
AMMONIUM CHLORIDES
FABRIC FILTERS
ORE PROCESSING
POLYMERS
REMOVAL
SOLIDS
SUSPENSIONS
AMIDES
AMMONIUM COMPOUNDS
AMMONIUM HALIDES
CHLORIDES
CHLORINE COMPOUNDS
DISPERSIONS
DISSOLUTION
FILTERS
HALIDES
HALOGEN COMPOUNDS
ORES
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
PROCESSING
SEPARATION PROCESSES
050400* - Nuclear Fuels- Feed Processing