GB778061A - Improvements in or relating to recovery of uranium from naturally occurring materials - Google Patents

Improvements in or relating to recovery of uranium from naturally occurring materials

Info

Publication number
GB778061A
GB778061A GB1397653A GB1397653A GB778061A GB 778061 A GB778061 A GB 778061A GB 1397653 A GB1397653 A GB 1397653A GB 1397653 A GB1397653 A GB 1397653A GB 778061 A GB778061 A GB 778061A
Authority
GB
United Kingdom
Prior art keywords
uranium
solution
aqueous
relating
recovery
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
GB1397653A
Inventor
Francis Hereward Burstall
Thomas Victor Arden
Gervaise Luigi Milward
Geoffrey Arthur Wood
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 GB1397653A priority Critical patent/GB778061A/en
Publication of GB778061A publication Critical patent/GB778061A/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
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J41/00—Anion exchange; Use of material as anion exchangers; Treatment of material for improving the anion exchange properties
    • B01J41/04—Processes using organic exchangers

Landscapes

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

Abstract

In a process for the treatment of an aqueous sulphate solution containing uranium and ferric iron, the solution is brought into contact with an ion-exchange resin having at at exchange positions tertiary amino groups <FORM:0778061/III/1> where R1 and R2 are methyl and ethyl groups, the uranium is absorbed and subsequently eluted. The resin may be of a polystyrene type prepared by the emulsion polymerization of styrene in the presence of ethylene glycol dimethacrylate or divinyl benzene, treated with chloromethyl ether and finally with dimethylor diethylamine. The aqueous solution may have a pH of 1.2 to 1.8, and a molar ratio of iron to uranium of at least 10 to 1 and a ferric iron concentration of at least one tenth molar, and the uranium may be eluted by an aqueous ammonium nitrate solution acidified with nitric acid.
GB1397653A 1953-05-19 1953-05-19 Improvements in or relating to recovery of uranium from naturally occurring materials Expired GB778061A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB1397653A GB778061A (en) 1953-05-19 1953-05-19 Improvements in or relating to recovery of uranium from naturally occurring materials

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1397653A GB778061A (en) 1953-05-19 1953-05-19 Improvements in or relating to recovery of uranium from naturally occurring materials

Publications (1)

Publication Number Publication Date
GB778061A true GB778061A (en) 1957-07-03

Family

ID=10032779

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1397653A Expired GB778061A (en) 1953-05-19 1953-05-19 Improvements in or relating to recovery of uranium from naturally occurring materials

Country Status (1)

Country Link
GB (1) GB778061A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4427639A (en) 1978-02-06 1984-01-24 Himsley Engineering Limited Ion exchange process

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4427639A (en) 1978-02-06 1984-01-24 Himsley Engineering Limited Ion exchange process

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