GB1226198A - - Google Patents

Info

Publication number
GB1226198A
GB1226198A GB1226198DA GB1226198A GB 1226198 A GB1226198 A GB 1226198A GB 1226198D A GB1226198D A GB 1226198DA GB 1226198 A GB1226198 A GB 1226198A
Authority
GB
United Kingdom
Prior art keywords
dissolved
melt
dec
precipitate
carbide
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
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 DE19671592129 external-priority patent/DE1592129C/en
Application filed filed Critical
Publication of GB1226198A publication Critical patent/GB1226198A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • 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

1,226,198. Uranium fluorides. KERN FORSCHUNGSANLAGE JULICH G.m.b.H.. 20 Dec., 1968 [21 Dec., 1967], No. 60610/68. Heading C1A. [Also in Division G6] Spent nuclear fuel containing uranium and thorium oxide or carbide is dissolved in an alkali metal compound melt, and the solution is treated to precipitate an alkali metal uranate which is separated and fluorinated to form UF 6. In one embodiment, oxide fuel is dissolved in potassium pyrosulphate melt and solid NaOH is added to form the precipitate; in another embodiment, carbide fuel is dissolved in a NaOH » Na 2 O 2 or a Na 2 CO 3» K 2 CO 3 melt. Fluorination to UF 6 is carried out in a fluidized bed (a) with HF to form UO 2 F 2 and then with F 2 ; (b) with HF mixed with S0 2 or NH 3 to form UF 4 and then with F 2 ; or (c) directly with F 2 .
GB1226198D 1967-12-21 1968-12-20 Expired GB1226198A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19671592129 DE1592129C (en) 1967-12-21 1967-12-21 Process for the reprocessing of nuclear fuel elements

Publications (1)

Publication Number Publication Date
GB1226198A true GB1226198A (en) 1971-03-24

Family

ID=5680233

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1226198D Expired GB1226198A (en) 1967-12-21 1968-12-20

Country Status (2)

Country Link
FR (1) FR1596241A (en)
GB (1) GB1226198A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1996032729A1 (en) * 1995-04-12 1996-10-17 British Nuclear Fuels Plc Method of processing oxide nuclear fuel
GB2341396A (en) * 1998-09-11 2000-03-15 Toshiba Kk Molten salt electrolysis of nuclear waste

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1996032729A1 (en) * 1995-04-12 1996-10-17 British Nuclear Fuels Plc Method of processing oxide nuclear fuel
GB2341396A (en) * 1998-09-11 2000-03-15 Toshiba Kk Molten salt electrolysis of nuclear waste
GB2341396B (en) * 1998-09-11 2001-05-23 Toshiba Kk Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same
US6299748B1 (en) 1998-09-11 2001-10-09 Kabushiki Kaisha Toshiba Method and apparatus of treating waste from nuclear fuel handling facility
US6736951B2 (en) 1998-09-11 2004-05-18 Kabushiki Kaisha Toshiba Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same

Also Published As

Publication number Publication date
DE1592129B2 (en) 1972-08-24
DE1592129A1 (en) 1972-03-09
FR1596241A (en) 1970-06-15

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee