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 Ferric leaching of uranium values from lignite

Details
Inventors: Schultze, Lawrence E.; Bauer, Donald J.; Morimoto, Michael T.;
Assignee: The United States of America as represented by the Secretary of the (Washington, DC)
Primary Examiner: Miller; Edward A.
Assistant Examiner:
Attorney, Agent or Firm: Brown; William S., Gardiner; Donald A.

There is disclosed a process for extracting uranium values from a uranium-containing carbonaceous ore such as lignite. This process includes the step of treating the ore with an aqueous leach solution containing a water-soluble ferric salt.

DETAILED DESCRIPTION We claim: 1.
A process for extracting uranium values from a uraniterous lignite consisting essentially of treating the lignite at a temperature of from about 20.
degree.
to 104.
degree.
C.
with a leach solution consisting essentially of an aqueous solution of a ferric salt.
2.
The process of claim 1 wherein said ferric salt is present in said leach solution in a concentration of from about 0.
8 to 3.
4 molar.
3.
The process of claim 1 wherein said ferric salt is ferric sulfate.
4.
The process of claim 1 wherein said ferric salt is ferric chloride.
5.
The process of claim 1 wherein said leach solution further includes a minor amount of a mineral acid having the same anion as the anion of said ferric salt.
6.
The process of claim 1 wherein said lignite is treated for a period of time in the range of about two to four hours.




Description:
TECHNICAL FIELD This invention relates to a process for extracting uranium values from uranium-containing carbonaceous ores.
BACKGROUND ART It is known to treat a uranium-containing oxide ore, such as pitchblende, by roasting the ore with 10% anhydrous metallic sulfide, such as FeS.
sub.
2 (pyrite), at gradually increasing temperature.
Exemplary of this type of prior art is U.
S.
Pat.
No.
3,152,862 to Fischer.
Furthermore, the use of ferric salts for extracting uranium from non-carbonaceous ores is known.
Illustrative of this type of prior art are U.
S.
Pat.
Nos.
2,570,120 to Handley et al, 2,736,634 to Gaudin et al, 2,737,438 to Gaudin, 2,847,275 to Yeager, and 2,894,804 to Sawyer et al.
Sawyer et al use a ferric chloride leaching solution containing usually 2-15 pounds FeCl.
sub.
3.
6H.
sub.
2 O per pound of uranium values to be recovered.
Gaudin et al use a sulfuric acid leaching solution containing ferric ion, with ferric sulfate or ferric chloride being exemplary sources of the ferric ion.
The leaching solution contains an amount of sulfuric acid (sp.
gr.
1.
84) that is greater than or equal to the amount of ferric salt, on a weight basis



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