GB905371A - Method of producing uranium dioxide powder - Google Patents

Method of producing uranium dioxide powder

Info

Publication number
GB905371A
GB905371A GB41939/60A GB4193960A GB905371A GB 905371 A GB905371 A GB 905371A GB 41939/60 A GB41939/60 A GB 41939/60A GB 4193960 A GB4193960 A GB 4193960A GB 905371 A GB905371 A GB 905371A
Authority
GB
United Kingdom
Prior art keywords
uranyl
less
sintered
hours
concentration
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
GB41939/60A
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.)
Mitsubishi Metal Corp
Original Assignee
Mitsubishi Metal Corp
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 Mitsubishi Metal Corp filed Critical Mitsubishi Metal Corp
Publication of GB905371A publication Critical patent/GB905371A/en
Expired legal-status Critical Current

Links

Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B82—NANOTECHNOLOGY
    • B82Y—SPECIFIC USES OR APPLICATIONS OF NANOSTRUCTURES; MEASUREMENT OR ANALYSIS OF NANOSTRUCTURES; MANUFACTURE OR TREATMENT OF NANOSTRUCTURES
    • B82Y30/00—Nanotechnology for materials or surface science, e.g. nanocomposites
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/50—Agglomerated particles
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/60—Particles characterised by their size
    • C01P2004/61—Micrometer sized, i.e. from 1-100 micrometer
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/60—Particles characterised by their size
    • C01P2004/62—Submicrometer sized, i.e. from 0.1-1 micrometer
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/60—Particles characterised by their size
    • C01P2004/64—Nanometer sized, i.e. from 1-100 nanometer
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Nanotechnology (AREA)
  • Organic Chemistry (AREA)
  • Condensed Matter Physics & Semiconductors (AREA)
  • Inorganic Chemistry (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • General Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Materials Engineering (AREA)
  • Composite Materials (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Powdered VO2 is formed by thermally decomposing ammonium diuranate, which has been precipitated from an aqueous solution of a refined uranyl salt of 100 gm./l. or less U concentration, into UO3 or U3O8 which are then reduced and sintered in a current of a gas containing free H2, e.g. H2, H2 and N2, or NH3 (which decomposes to yield hydrogen at the temperature employed), at 1200 DEG - 1750 DEG C. The precipitation conditions are a concentration of not more than 28% for the NH4OH which is added to the uranyl salt solution, e.g. uranyl nitrate or a mixture of HF and uranyl fluoride, at a rate of 100 g. NH3/Kg.U/min. or less at a reaction temperature of 100 DEG C. or less to give a pH, e.g. 6-7, sufficient to complete the precipitation. The ammonium diuranate may be filtered, dried, pulverized and then calcined for 3 hours at e.g. 400 DEG or 700 DEG C. in a furnace in a current of air giving UO3 or U3O8 respectively, which is then reduced and sintered for 3 hours. The UO2 produced is ground, after cooling, to a powder which is suitable for use as a nuclear fuel material, e.g. by swaying, pelleting and extrusion.
GB41939/60A 1960-01-30 1960-12-06 Method of producing uranium dioxide powder Expired GB905371A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP258860 1960-01-30

Publications (1)

Publication Number Publication Date
GB905371A true GB905371A (en) 1962-09-05

Family

ID=11533520

Family Applications (1)

Application Number Title Priority Date Filing Date
GB41939/60A Expired GB905371A (en) 1960-01-30 1960-12-06 Method of producing uranium dioxide powder

Country Status (2)

Country Link
DE (1) DE1240055B (en)
GB (1) GB905371A (en)

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1034606B (en) * 1956-09-29 1958-07-24 Degussa Process for the separation of nuclear-pure ammonium urate
US2906598A (en) * 1958-04-14 1959-09-29 John M Googin Preparation of high density uo2

Also Published As

Publication number Publication date
DE1240055B (en) 1967-05-11

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