GB906020A - Improved anion-exchange process for uranium recovery - Google Patents

Improved anion-exchange process for uranium recovery

Info

Publication number
GB906020A
GB906020A GB885358A GB885358A GB906020A GB 906020 A GB906020 A GB 906020A GB 885358 A GB885358 A GB 885358A GB 885358 A GB885358 A GB 885358A GB 906020 A GB906020 A GB 906020A
Authority
GB
United Kingdom
Prior art keywords
anion exchange
particles
uranium
pulp
polymeric material
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
GB885358A
Inventor
David Anthony Everest
Gordon Henry Elliott Sims
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 GB885358A priority Critical patent/GB906020A/en
Publication of GB906020A publication Critical patent/GB906020A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Organic Chemistry (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Environmental & Geological Engineering (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Geology (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture Of Macromolecular Shaped Articles (AREA)

Abstract

In the recovery of uranium from aqueous solutions, there is employed an anion exchange medium consisting of an inert polymeric material to whose surface are bonded particles of anionexchange resin which are between 0,3 and 2,0 mm. diameter. The inert polymeric material may be thermoplastic, for example polyethylene, polyisobutylene, vulcanized natural or synthetic rubber, especially polystyrene and a copolymer of styrene and butadiene, and a copolymer of butadiene and acrylonitrile, vinyl chloride polymers and copolymers, for example polyvinyl chloride and the copolymers of vinyl chloride with the vinyl esters of lower aliphatic acids, for example vinyl acetate. The anion exchange medium may be formed by heating a mixture of the anion exchange particles with the polymeric material, dispersing the particles, and forming into for example a sheet. In an example, an anion exchange resin, prepared by treating particles of chloromethylated polystyrene cross-linked with divinylbenzene with trimethylamine, was formed into a sheet with polyethylene, treated with sulphuric acid, and used to absorb uranium from a uranyl sulphate solution. The process may be applied to recovery of uranium from aqueous pulps, wherein the anion exchange medium is immersed in the pulp so as to extend upwardly therein, and the solid particles present in the pulp are kept suspended by gas forced upwardly through the pulp.
GB885358A 1958-03-19 1958-03-19 Improved anion-exchange process for uranium recovery Expired GB906020A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB885358A GB906020A (en) 1958-03-19 1958-03-19 Improved anion-exchange process for uranium recovery

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB885358A GB906020A (en) 1958-03-19 1958-03-19 Improved anion-exchange process for uranium recovery

Publications (1)

Publication Number Publication Date
GB906020A true GB906020A (en) 1962-09-19

Family

ID=9860505

Family Applications (1)

Application Number Title Priority Date Filing Date
GB885358A Expired GB906020A (en) 1958-03-19 1958-03-19 Improved anion-exchange process for uranium recovery

Country Status (1)

Country Link
GB (1) GB906020A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4406865A (en) 1978-12-15 1983-09-27 Exxon Research And Engineering Co. Metal extraction by solid-liquid agglomerates
RU2797892C1 (en) * 2022-04-25 2023-06-09 Акционерное общество "Хиагда" (АО "Хиагда") Method for sorption extraction of uranium from sulfuric acid solutions of underground leaching characterized by low temperature

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4406865A (en) 1978-12-15 1983-09-27 Exxon Research And Engineering Co. Metal extraction by solid-liquid agglomerates
RU2797892C1 (en) * 2022-04-25 2023-06-09 Акционерное общество "Хиагда" (АО "Хиагда") Method for sorption extraction of uranium from sulfuric acid solutions of underground leaching characterized by low temperature

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