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GB928875A - Preparation of uranium-aluminum alloys - Google Patents

Preparation of uranium-aluminum alloys

Info

Publication number
GB928875A
GB928875A GB457162A GB457162A GB928875A GB 928875 A GB928875 A GB 928875A GB 457162 A GB457162 A GB 457162A GB 457162 A GB457162 A GB 457162A GB 928875 A GB928875 A GB 928875A
Authority
GB
United Kingdom
Prior art keywords
uranium
chloride
halide
alloys
preparation
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
GB457162A
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.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
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 US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Publication of GB928875A publication Critical patent/GB928875A/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
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C1/00Making non-ferrous alloys
    • C22C1/02Making non-ferrous alloys by melting
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C43/00Alloys containing radioactive materials
    • 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

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

U-Al alloys are prepared by dissolving a uranium halide, particularly the chloride, in an approximately equimolar molten mixture of alkali metal halide and aluminium halide and adding a stoichiometric excess of metallic Al to the salt solution to form U which alloys with the excess Al. The halides in the salt mixture contain chloride and bromide in a mol. ratio between 9 and 13. The uranium chloride can be formed in situ by adding uranium oxide to the molten salt mixture. A chlorinating agent e.g. CCl4, Cl or COCl2, may be fed to the melt.
GB457162A 1961-04-20 1962-02-06 Preparation of uranium-aluminum alloys Expired GB928875A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US10448561 US3052537A (en) 1961-04-20 1961-04-20 Preparation of uranium alum-inum alloys

Publications (1)

Publication Number Publication Date
GB928875A true GB928875A (en) 1963-06-19

Family

ID=22300755

Family Applications (1)

Application Number Title Priority Date Filing Date
GB457162A Expired GB928875A (en) 1961-04-20 1962-02-06 Preparation of uranium-aluminum alloys

Country Status (3)

Country Link
US (1) US3052537A (en)
CH (1) CH430225A (en)
GB (1) GB928875A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1212304B (en) * 1963-08-19 1966-03-10 Comision Nac De En Atomica Process for the production of aluminum-uranium alloys
US3377161A (en) * 1965-10-11 1968-04-09 Comision Nac De En Atomica Process for the production of an aluminum-uranium alloy
US4509978A (en) * 1982-12-07 1985-04-09 The United States Of America As Represented By The United States Department Of Energy Recoverable immobilization of transuranic elements in sulfate ash
CN105132953B (en) * 2015-07-24 2017-11-21 中国原子能科学研究院 A kind of spentnuclear fuel dry method post-processing approach for being used to directly obtain zircaloy fuel

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB799662A (en) * 1953-03-10 1958-08-13 Atomic Energy Authority Uk Production of plutonium-aluminium alloys
US2948586A (en) * 1958-07-24 1960-08-09 Raymond H Moore Fused salt process for recovery of values from used nuclear reactor fuels

Also Published As

Publication number Publication date
US3052537A (en) 1962-09-04
CH430225A (en) 1967-02-15

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