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GB840311A - A fluoride volatility process for the recovery of uranium - Google Patents

A fluoride volatility process for the recovery of uranium

Info

Publication number
GB840311A
GB840311A GB1668054A GB1668054A GB840311A GB 840311 A GB840311 A GB 840311A GB 1668054 A GB1668054 A GB 1668054A GB 1668054 A GB1668054 A GB 1668054A GB 840311 A GB840311 A GB 840311A
Authority
GB
United Kingdom
Prior art keywords
bromine
trifluoride
pentafluoride
uranium
monofluoride
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
GB1668054A
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 GB1668054A priority Critical patent/GB840311A/en
Publication of GB840311A publication Critical patent/GB840311A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/04Halides of uranium
    • C01G43/06Fluorides
    • C01G43/063Hexafluoride (UF6)
    • C01G43/066Preparation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • 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
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • 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
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Material containing uranium is treated with halogen fluoride in the liquid phase, the product is fractionally distilled, and a uranium hexafluoride-rich fraction is separately collected. The preferred halogen fluoride is bromine trifluoride, but other fluorides referred to are chlorine trifluoride, bromine monofluoride, bromine pentafluoride and iodine pentafluoride. Addition of bromine, antimony pentafluoride, niobium pentafluoride, or tin tetrafluoride to bromine trifluoride increases the reaction rate. In order to prevent formation of a volatile plutonium fluoride when using bromine trifluoride, bromine and bromine monofluoride may be continuously removed during the treatment by distillation or by addition of fluorine, which reacts to re-form bromine trifluoride. The process may be used to recover uranium from neutron-irradiated uranium metal or salts e.g. uranyl ammonium phosphate (see Group XL (a)). When using bromine trifluoride, by-products of the reaction (bromine and bromine monofluoride, or bromine pentafluoride) may be reacted with fluorine, or bromine at 150 DEG C. to reform bromine trifluoride for re-use.
GB1668054A 1954-06-04 1954-06-04 A fluoride volatility process for the recovery of uranium Expired GB840311A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB1668054A GB840311A (en) 1954-06-04 1954-06-04 A fluoride volatility process for the recovery of uranium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1668054A GB840311A (en) 1954-06-04 1954-06-04 A fluoride volatility process for the recovery of uranium

Publications (1)

Publication Number Publication Date
GB840311A true GB840311A (en) 1960-07-06

Family

ID=10081706

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1668054A Expired GB840311A (en) 1954-06-04 1954-06-04 A fluoride volatility process for the recovery of uranium

Country Status (1)

Country Link
GB (1) GB840311A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0036039A3 (en) * 1980-03-14 1982-01-13 Kernforschungszentrum Karlsruhe Gmbh Process for removing adherent, notably pulverulent deposits in apparatuses treating urane hexafluoride
RU2219132C2 (en) * 2002-02-13 2003-12-20 Федеральное государственное унитарное предприятие "Сибирский химический комбинат" Method for gasification of uranium nonvolatile compounds
CN120261011A (en) * 2025-03-31 2025-07-04 中核第七研究设计院有限公司 A method for separating and recovering uranium-containing radioactive waste

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0036039A3 (en) * 1980-03-14 1982-01-13 Kernforschungszentrum Karlsruhe Gmbh Process for removing adherent, notably pulverulent deposits in apparatuses treating urane hexafluoride
RU2219132C2 (en) * 2002-02-13 2003-12-20 Федеральное государственное унитарное предприятие "Сибирский химический комбинат" Method for gasification of uranium nonvolatile compounds
CN120261011A (en) * 2025-03-31 2025-07-04 中核第七研究设计院有限公司 A method for separating and recovering uranium-containing radioactive waste

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