GB2015975A - Uranium Recovery Process - Google Patents

Uranium Recovery Process

Info

Publication number
GB2015975A
GB2015975A GB7908727A GB7908727A GB2015975A GB 2015975 A GB2015975 A GB 2015975A GB 7908727 A GB7908727 A GB 7908727A GB 7908727 A GB7908727 A GB 7908727A GB 2015975 A GB2015975 A GB 2015975A
Authority
GB
United Kingdom
Prior art keywords
uranium
ammonia
precipitated
production
compound
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.)
Withdrawn
Application number
GB7908727A
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.)
Reaktor Brennelement Union GmbH
Original Assignee
Reaktor Brennelement Union GmbH
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
Priority claimed from DE19782810776 external-priority patent/DE2810776A1/en
Application filed by Reaktor Brennelement Union GmbH filed Critical Reaktor Brennelement Union GmbH
Publication of GB2015975A publication Critical patent/GB2015975A/en
Withdrawn legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • 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
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0278—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methods

Landscapes

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

Abstract

A method is disclosed for the recovery of uranium compounds from uranium-containing waste liquors produced in the AUC-conversion process for the production of UO2- nuclear fuel. The waste liquor is heated to about 95 DEG C in a single passage through an electrically operated continuous flow heater to liberate its carbon dioxide content to a concentration of less than 6 g per litre and ammonia. Uranium is precipitated in the form of a compound thereof from the residual solution at a temperature of 50 to 55 DEG C by addition of ammonia and hydrogen peroxide. The precipitated uranium compound may be converted to U3O8 at 800 DEG C and used in the production of UO2. The method is applicable to both fluorine-containing and nitrate- containing waste liquors.
GB7908727A 1978-03-13 1979-03-13 Uranium Recovery Process Withdrawn GB2015975A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19782810776 DE2810776A1 (en) 1978-03-13 1978-03-13 PROCESS FOR THE RECOVERY OF URANIUM COMPOUNDS FROM WASTE DURING AUC CONVERSION
DE2811559 1978-03-16

Publications (1)

Publication Number Publication Date
GB2015975A true GB2015975A (en) 1979-09-19

Family

ID=25774045

Family Applications (1)

Application Number Title Priority Date Filing Date
GB7908727A Withdrawn GB2015975A (en) 1978-03-13 1979-03-13 Uranium Recovery Process

Country Status (2)

Country Link
BR (1) BR7901555A (en)
GB (1) GB2015975A (en)

Also Published As

Publication number Publication date
BR7901555A (en) 1979-10-16

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Legal Events

Date Code Title Description
WAP Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1)