GB846861A - Process of recovering uranium - Google Patents

Process of recovering uranium

Info

Publication number
GB846861A
GB846861A GB3281845A GB3281845A GB846861A GB 846861 A GB846861 A GB 846861A GB 3281845 A GB3281845 A GB 3281845A GB 3281845 A GB3281845 A GB 3281845A GB 846861 A GB846861 A GB 846861A
Authority
GB
United Kingdom
Prior art keywords
uranium
solution
tetrachloride
calutron
treated
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
GB3281845A
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
Publication of GB846861A publication Critical patent/GB846861A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B15/00Peroxides; Peroxyhydrates; Peroxyacids or salts thereof; Superoxides; Ozonides
    • C01B15/04Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof
    • C01B15/047Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof of heavy metals
    • C01B15/0475Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof of heavy metals of actinides
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • 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
    • 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
    • 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
    • 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

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

Abstract

In the separation of isotopes of uranium by means of a calutron, such as is described in Specification 816,772, by vaporization of a charge of uranium tetrachloride, the uranium values are recovered from parts of the calutron by washing them with a solvent for uranium whereby metal impurities including iron are introduced into the wash solution; the pH of the solution is then adjusted to 1:3, the solution refrigerated to produce ice crystals therein and then treated with hydrogen peroxide thereby precipitating uranium peroxide. The uranium peroxide may be calcined to the trioxide and the latter reacted with carbon tetrachloride to produce uranium pentachloride which on calcining <PICT:0846861/III/1> gives uranium tetrachloride for recycling to the calutron, or alternatively the uranium trioxide may first be reduced by methane to the dioxide and thereafter reacted with calcium tetrachloride to give uranium tetrachloride direct. As shown in Fig. 3, a solution derived from washing or acid treating parts of the calutron to take up the uranium values and generally contaminated with copper, iron, chromium and nickel, is first treated with carbonate-free ammonium hydroxide solution or excess ammonia gas thereby precipitating ammonium diuranate and the hydroxides of iron and chromium away from the copper and nickel which remain in solution as amine complexes. The precipitate after washing is taken up in nitric acid and depending on its ferric ion content is, or is not, treated with a complexing agent such as lactic acid, acetic acid or a fluoride ion thereby inhibiting the catalytic decomposing effects of the ferric ion on hydrogen peroxide. If the ferric ion content is below 3% this is not necessary. In either case the solution is then treated with ammonium hydroxide to adjust the pH between 1 and 3 and the solution thereafter cooled below its freezing point to form minute ice crystals. Pre-cooled hydrogen peroxide is added in excess and the solution is refrigerated to a solid mass at temperature for example of -45 DEG C. It is then thawed to the incipient freezing p range namely -2 to -10 DEG C. whereupon the solution may be filtered and the precipitate of uranium peroxide washed with an aqueous solution containing ammonium nitrate and hydrogen peroxide.
GB3281845A 1944-11-30 1945-12-04 Process of recovering uranium Expired GB846861A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US846861XA 1944-11-30 1944-11-30

Publications (1)

Publication Number Publication Date
GB846861A true GB846861A (en) 1960-08-31

Family

ID=22186584

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3281845A Expired GB846861A (en) 1944-11-30 1945-12-04 Process of recovering uranium

Country Status (1)

Country Link
GB (1) GB846861A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0054014A1 (en) * 1980-11-24 1982-06-16 FMC Corporation Method of removing phosphorus impurities from yellowcake
CN103397184A (en) * 2013-07-31 2013-11-20 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction
CN113406180A (en) * 2021-06-07 2021-09-17 核工业北京地质研究院 Method for confirming favorable temperature range of enriched uranium with pH value change
CN116354314A (en) * 2021-12-27 2023-06-30 核工业北京化工冶金研究院 Method for improving nitric acid solubility of uranium peroxide product

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0054014A1 (en) * 1980-11-24 1982-06-16 FMC Corporation Method of removing phosphorus impurities from yellowcake
CN103397184A (en) * 2013-07-31 2013-11-20 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction
CN103397184B (en) * 2013-07-31 2014-12-03 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction
CN113406180A (en) * 2021-06-07 2021-09-17 核工业北京地质研究院 Method for confirming favorable temperature range of enriched uranium with pH value change
CN113406180B (en) * 2021-06-07 2022-12-20 核工业北京地质研究院 Method for confirming favorable temperature range of enriched uranium with pH value change
CN116354314A (en) * 2021-12-27 2023-06-30 核工业北京化工冶金研究院 Method for improving nitric acid solubility of uranium peroxide product

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