GB760191A - Sulphur dioxide leaching of uranium containing material - Google Patents

Sulphur dioxide leaching of uranium containing material

Info

Publication number
GB760191A
GB760191A GB2938354A GB2938354A GB760191A GB 760191 A GB760191 A GB 760191A GB 2938354 A GB2938354 A GB 2938354A GB 2938354 A GB2938354 A GB 2938354A GB 760191 A GB760191 A GB 760191A
Authority
GB
United Kingdom
Prior art keywords
sulphur dioxide
solution
uranium
iron
soluble
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
GB2938354A
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.)
Minister of Mines and Technical Surveys
Original Assignee
Minister of Mines and Technical Surveys
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 Minister of Mines and Technical Surveys filed Critical Minister of Mines and Technical Surveys
Publication of GB760191A publication Critical patent/GB760191A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0234Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agent

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)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

Uranium is recovered from iron-free finely divided material containing uranium at least in part in the tetravalent form by leaching the material with an aqueous solution containing sulphur dioxide in the presence of a soluble ferric or ferrous salt, and/or a soluble manganese salt, the solution being aerated during the leaching. The solution should contain 1-2 grams of iron per litre as a soluble salt or 0.5-1 grams of manganese sulphate per litre. After separation from the undissolved residue the uranium may be precipitated from the solution by adjusting the pH to 1.25 and adding iron powder in the presence of a soluble phosphate, arsenate or fluoride. The uranium material employed which may contain hexavalent uranium, such as pitch blende and may be constituted by uranium ore or mill tailings, is first freed of free iron by magnetic separation and thereafter formed into a pulp having a liquid solid ratio of from 1:1 to 2:1 with an aqueous sulphur dioxide solution made from water or barren recycled solution by introducing sulphur dioxide from a sulphur burner or roaster or from return processed gas, thereinto. The pulp is agitated with air at atmospheric temperature and pressure in the presence of the soluble iron or manganese salt preferably as sulphate, and the pH of the solution maintained at 1-2 by the addition preferably intermittently, of sulphur dioxide gas. The aeration should be controlled to avoid excessive removal of sulphur dioxide. If desired the leaching may be effected by percolating an aqueous solution containing sulphur dioxide with aeration through a bed of the material. In either event the resulting solution, after filtration if necessary, is adjusted to pH 1.25 by the addition of sulphur dioxide gas, and the soluble phosphate fluoride or arsenate is added together with finely divided iron powder. The precipitated slurry is treated to remove magnetically the excess metallic iron and the resulting slurry is vacuum filtered to recover excess sulphur dioxide which may be recycled to the precipitation step.
GB2938354A 1953-10-20 1954-10-12 Sulphur dioxide leaching of uranium containing material Expired GB760191A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA760191X 1953-10-20

Publications (1)

Publication Number Publication Date
GB760191A true GB760191A (en) 1956-10-31

Family

ID=4172381

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2938354A Expired GB760191A (en) 1953-10-20 1954-10-12 Sulphur dioxide leaching of uranium containing material

Country Status (1)

Country Link
GB (1) GB760191A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2424964A1 (en) * 1978-05-05 1979-11-30 Cogema IMPROVEMENTS IN PROCESSES FOR PROCESSING URANIFEROUS ORE
GB2198723A (en) * 1986-12-18 1988-06-22 British Petroleum Co Plc Separating uranium from uranium bearing materials

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2424964A1 (en) * 1978-05-05 1979-11-30 Cogema IMPROVEMENTS IN PROCESSES FOR PROCESSING URANIFEROUS ORE
GB2198723A (en) * 1986-12-18 1988-06-22 British Petroleum Co Plc Separating uranium from uranium bearing materials

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