GB716597A - Leaching of uranium - Google Patents

Leaching of uranium

Info

Publication number
GB716597A
GB716597A GB3308852A GB3308852A GB716597A GB 716597 A GB716597 A GB 716597A GB 3308852 A GB3308852 A GB 3308852A GB 3308852 A GB3308852 A GB 3308852A GB 716597 A GB716597 A GB 716597A
Authority
GB
United Kingdom
Prior art keywords
uranium
alkali metal
sodium
carbonate
oxygen
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
GB3308852A
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.)
National Research Council of Canada
Original Assignee
National Research Council of Canada
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 National Research Council of Canada filed Critical National Research Council of Canada
Publication of GB716597A publication Critical patent/GB716597A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0247—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling

Landscapes

  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Environmental & Geological Engineering (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Material containing uranium in a valence state less than six is treated with an aqueous solution of alkali metal carbonate at a temperature between 150 and 300 DEG F. in a closed reaction zone, in the presence of gaseous molecular oxygen under a partial pressure of not less than 3 p.s.i., the solution of uranium formed being separated from the residue. Alkali metal bicarbonate may be added or may be formed by the reaction of the alkali metal carbonate and the components of the ore in the presence of oxygen. Excessive alkali metal bicarbonate formed may be reconverted to the carbonate by the addition of sodium hydroxide or lime. The function of the sodium bicarbonate is to neutralise any caustic soda produced and thereby to prevent the formation of insoluble sodium uranate, sodium uranyl carbonate only being formed if the amount of caustic soda present is limited. The oxygen partial pressure is preferably between 10 and 30 p.s.i. The process is applicable to the treatment of materials such as uraninite thucholite, pitchblende, materials containing uranium metal, uranous oxide and uranium sulphide, in which uranium is present in a valence state less than 6; it is also applicable to materials in which the uranium occurs in association with substances which in order to extract the uranium become oxidized themselves. A table compares the effects of various leaching periods, various alkali metal carbonate concentrations, oxygen pressures and temperatures. Included in the term alkali metal carbonate are the carbonates and bicarbonates of lithium, sodium, potassium, rubidium, caesium, and ammonium.
GB3308852A 1952-01-11 1952-12-31 Leaching of uranium Expired GB716597A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA716597X 1952-01-11

Publications (1)

Publication Number Publication Date
GB716597A true GB716597A (en) 1954-10-06

Family

ID=4172239

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3308852A Expired GB716597A (en) 1952-01-11 1952-12-31 Leaching of uranium

Country Status (2)

Country Link
FR (1) FR1069426A (en)
GB (1) GB716597A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1096887B (en) * 1957-12-17 1961-01-12 Commissariat Energie Atomique Process for the extraction of uranium from alkaline, oxidized lyes
EP0005420A1 (en) * 1978-05-08 1979-11-14 Boliden Aktiebolag A method of purifying a substance by the selective alkaline carbonate leaching of said substance to remove uranium therefrom

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
OA06179A (en) * 1978-02-09 1981-06-30 Pechiney Aluminium High temperature attack of ores by a liquor containing essentially a soluble bicarbonate.
FR2432554A1 (en) * 1978-08-01 1980-02-29 Pechiney Ugine Kuhlmann Uran Oxidative pressure leaching of uranium minerals - using potassium carbonate-bi:carbonate liquor to improve uranium yield
FR2462482A1 (en) * 1979-07-27 1981-02-13 Pechiney Aluminium Continuous hot oxidative leaching of uranium mineral - using recycle soln. with high uranium and low alkali meta (bi) carbonate contents (SE 2.3.81)
FR2475065A2 (en) * 1979-07-27 1981-08-07 Pechiney Aluminium PROCESS FOR THE OXIDIZING ATTACK OF A URANIUM BY A CARBONATE LIQUOR
FR2545105A1 (en) * 1983-04-27 1984-11-02 Pechiney Uranium High-temperature pretreatment of uraniferous, vanadiferous or molybdeniferous ores containing clayey gangue by means of an alkaline aqueous solution
FR2552108A1 (en) * 1983-09-21 1985-03-22 Pechiney Uranium High-temperature pretreatment by means of an alkaline aqueous solution of ores with a clayey gangue containing at least one upgradable element other than uranium, vanadium and molybdenum.
PH20901A (en) * 1983-04-27 1987-05-27 Pechiney Uranium High-temperature pretreatment by means of an alkaline aqueous solution of ores having an argillaceous gangue containg at least one usable element
FR2567419A1 (en) * 1984-07-13 1986-01-17 Pechiney Uranium Pretreatment of natural materials with clayey gangue containing at least one reclaimable element by means of an aqueous solution of alkali metal silicate or aluminate

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1096887B (en) * 1957-12-17 1961-01-12 Commissariat Energie Atomique Process for the extraction of uranium from alkaline, oxidized lyes
EP0005420A1 (en) * 1978-05-08 1979-11-14 Boliden Aktiebolag A method of purifying a substance by the selective alkaline carbonate leaching of said substance to remove uranium therefrom

Also Published As

Publication number Publication date
FR1069426A (en) 1954-07-07

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