GB802452A - Improvements in a method of recovering uranium from ores containing it - Google Patents

Improvements in a method of recovering uranium from ores containing it

Info

Publication number
GB802452A
GB802452A GB18137/56A GB1813756A GB802452A GB 802452 A GB802452 A GB 802452A GB 18137/56 A GB18137/56 A GB 18137/56A GB 1813756 A GB1813756 A GB 1813756A GB 802452 A GB802452 A GB 802452A
Authority
GB
United Kingdom
Prior art keywords
solution
ore
leaching
nickel
catalyst
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB18137/56A
Inventor
Jean Le Bris
Pierre Mouret
Paul Pottier
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB802452A publication Critical patent/GB802452A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • C01G43/025Uranium dioxide

Abstract

Hydrated uranium dioxide is recovered by precipitation with nascent hydrogen from a solution of a hexavalent uranyl-alkali metal or -ammonium carbonate solution obtained from a uranium ore. The solution may be obtained, e.g. by directly leaching the ore with sodium carbonate or bicarbonate (with an oxidizing agent if necessary) or by treating with an excess of sodium carbonate the product of acid leaching (with an oxidizing agent if necessary). In examples, the former method is used, the leaching being performed at 70 DEG or 80 DEG C. The nascent hydrogen is preferably generated by electrolysis of the solution (see Group XXXVI) in the presence of a hydrogenation catalyst such as nickel, platinum, palladium, iron or mercury or alloys thereof such as an aluminium/nickel alloy. The catalyst may be finely divided and used as a suspension or may be in the form of a fine grid, preferably located close to the cathode. After removal of the hydrated uranium oxide, the solution can be reused to attack further quantities of the ore. A nickel catalyst, if used, may be separated from the precipitate magnetically.
GB18137/56A 1955-06-20 1956-06-12 Improvements in a method of recovering uranium from ores containing it Expired GB802452A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR802452X 1955-06-20

Publications (1)

Publication Number Publication Date
GB802452A true GB802452A (en) 1958-10-08

Family

ID=9248121

Family Applications (1)

Application Number Title Priority Date Filing Date
GB18137/56A Expired GB802452A (en) 1955-06-20 1956-06-12 Improvements in a method of recovering uranium from ores containing it

Country Status (1)

Country Link
GB (1) GB802452A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2510095A1 (en) * 1981-07-22 1983-01-28 Metallgesellschaft Ag PROCESS FOR PRECIPITATION OF URANIUM OXIDE IN SOLDER CARBONATE SOLUTIONS BY REDUCTION BY METAL IRON

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2510095A1 (en) * 1981-07-22 1983-01-28 Metallgesellschaft Ag PROCESS FOR PRECIPITATION OF URANIUM OXIDE IN SOLDER CARBONATE SOLUTIONS BY REDUCTION BY METAL IRON

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