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

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

Similar Documents

Publication Publication Date Title
US2906598A (en) Preparation of high density uo2
ES378984A1 (en) Process for the manufacture of nitrous oxide
GB1127707A (en) Improvements in method of preparing uranium dioxide
US2868707A (en) Process of making a neutronic reactor fuel element composition
US3179491A (en) Method for preparing uranium dioxide
Bagnall et al. 516. Neptunium and plutonium trioxide hydrates
GB1349584A (en) Process for producing ammonium diuranate
GB850957A (en) A method of preparing fluoride-free uranium dioxide
GB1350923A (en) Method for preparing oxides of fissile materials
GB905371A (en) Method of producing uranium dioxide powder
GB946513A (en) Preparation of spherical uranium dioxide particles
GB893061A (en) Improvements in or relating to sintered uranium dioxide
CA1197069A (en) Method for preparing a sinterable uranium dioxide powder
KR950005255B1 (en) Uo2 pellet of a particle control method
GB937330A (en) Preparation of uo for nuclear reactor fuel pellets
GB1148228A (en) Improved urania sol forming method
ES8500188A1 (en) Process for making high quality nuclear fuel grade ammonium diuranate from uranyl fluoride solutions
RU2116972C1 (en) Method of preparing anhydrous plutonium trifluoride from plutonium hydride
CS201977B1 (en) Process for preparing semiproducts and products of sinterable ceramic nuclear fuels
US3622480A (en) Method of increasing the concentration of oyxgen-18 in an oxygen-containing compound
JPS6374916A (en) Production of uranium dioxide powder
JPS6379725A (en) Production of powdery uranium dioxide
GB1158535A (en) Method of making Uranium Dioxide more Reactive
GB953977A (en) Method for preparing uo compacts
GB975330A (en) Production of high-purity sinterable beryllium oxide