GB785602A - Improvements in or relating to extraction of uranium from its ores - Google Patents

Improvements in or relating to extraction of uranium from its ores

Info

Publication number
GB785602A
GB785602A GB2298548A GB2298548A GB785602A GB 785602 A GB785602 A GB 785602A GB 2298548 A GB2298548 A GB 2298548A GB 2298548 A GB2298548 A GB 2298548A GB 785602 A GB785602 A GB 785602A
Authority
GB
United Kingdom
Prior art keywords
uranium
treated
phase
solution
acid
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
GB2298548A
Inventor
Thomas Victor Arden
Francis Hereward Burstall
Reginald Patrick Linstead
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB2298548A priority Critical patent/GB785602A/en
Publication of GB785602A publication Critical patent/GB785602A/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
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
    • 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
    • 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
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0278Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methods
    • C22B60/0282Solutions containing P ions, e.g. treatment of solutions resulting from the leaching of phosphate ores or recovery of uranium from wet-process phosphoric acid
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02PCLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00Technologies related to metal processing
    • Y02P10/20Recycling

Landscapes

  • General Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

Uranium is extracted from phosphatic ores containing it by treating the ore with sulphuric acid of substantially 1.84 specific gravity, to decompose phosphates present and form a system comprising a liquid sulphuric acidphosphoric acid phase and a solid phase containing substantially all of the uranium from the ore, and thereafter separating the solid phase from the liquid phase and working it up to recover uranium. The solids are preferably separated from the liquid by centrifugal means and afterwards taken up with water to dissolve the uranium and the solution treated with a soluble barium salt and filtered. The remaining solution is then treated with sodium hydroxide, ammonia or magnesium oxide to precipitate metals, including uranium, as hydroxides. Thereafter the separated and washed hydroxides are brought into nitric acid solution, from which the uranium may be extracted by means of diethyl ether or other organic solvent. According to an example, monazite was treated with sulphuric acid and heated to 220 DEG C. for two hours, and after cooling the solids were separated from the liquid. The solids were taken up with water and the resulting solution after dilution, was treated with gelatin and barium nitrate, the barium sulphate so formed acting as a collector for the mesothorium and the gelatin floculating the silica present. The filtrate was treated with caustic soda and the precipitate obtained after washing was taken up in nitric acid leaving an insoluble residue of thorium and ceric phosphates. The insoluble residue was, after separation, boiled with caustic soda, filtered, washed, dissolved in nitric acid and returned to the main solution. The combined solutions, optionally in the presence of a salting out agent such as ammonium nitrate, were subjected to a solvent extraction with, for example, a mixture of diethyl ether, tetrahydrosylvane and nitric acid, the acid being present to reduce extraction thereof from the aqueous phase. The residual aqueous solution may be treated for the recovery of thorium and rare earths whilst the organic phase contained uranium, thorium and cerium. The uranium may be recovered for example by treating the organic solvent phase with water to obtain an aqueous solution from which the uranium may be precipitated with hydrogen peroxide as uranium peroxide. Specification 781,721 is referred to.
GB2298548A 1948-08-31 1948-08-31 Improvements in or relating to extraction of uranium from its ores Expired GB785602A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB2298548A GB785602A (en) 1948-08-31 1948-08-31 Improvements in or relating to extraction of uranium from its ores

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2298548A GB785602A (en) 1948-08-31 1948-08-31 Improvements in or relating to extraction of uranium from its ores

Publications (1)

Publication Number Publication Date
GB785602A true GB785602A (en) 1957-10-30

Family

ID=10188228

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2298548A Expired GB785602A (en) 1948-08-31 1948-08-31 Improvements in or relating to extraction of uranium from its ores

Country Status (1)

Country Link
GB (1) GB785602A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2474056A1 (en) * 1980-01-23 1981-07-24 Israel Atomic Energy Comm Winning uranium from phosphorite - by leaching with sulphuric acid and reducing agent so gypsum and tetra:valent uranium are coprecipitated
EP0079190A2 (en) * 1981-11-09 1983-05-18 Exxon Research And Engineering Company The removal of solids from wet process phosphoric acid
CN114686681A (en) * 2020-12-30 2022-07-01 中核通辽铀业有限责任公司 Remote uranium deposit resource recovery system and method

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2474056A1 (en) * 1980-01-23 1981-07-24 Israel Atomic Energy Comm Winning uranium from phosphorite - by leaching with sulphuric acid and reducing agent so gypsum and tetra:valent uranium are coprecipitated
EP0079190A2 (en) * 1981-11-09 1983-05-18 Exxon Research And Engineering Company The removal of solids from wet process phosphoric acid
EP0079190A3 (en) * 1981-11-09 1984-02-08 Exxon Research And Engineering Company The removal of solids from wet process phosphoric acid
CN114686681A (en) * 2020-12-30 2022-07-01 中核通辽铀业有限责任公司 Remote uranium deposit resource recovery system and method
CN114686681B (en) * 2020-12-30 2023-10-20 中核通辽铀业有限责任公司 Remote uranium deposit resource recovery system and method

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