GB954720A - Improvements in or relating to reactor fuels - Google Patents

Improvements in or relating to reactor fuels

Info

Publication number
GB954720A
GB954720A GB12641/62A GB1264162A GB954720A GB 954720 A GB954720 A GB 954720A GB 12641/62 A GB12641/62 A GB 12641/62A GB 1264162 A GB1264162 A GB 1264162A GB 954720 A GB954720 A GB 954720A
Authority
GB
United Kingdom
Prior art keywords
uranium
plutonium
carbide
oxygen
powder
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
GB12641/62A
Inventor
Lewis Eric Russell
John David Lawrence Harrison
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
Priority to BE630429D priority Critical patent/BE630429A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB12641/62A priority patent/GB954720A/en
Priority to DEU9686A priority patent/DE1294573B/en
Priority to FR929953A priority patent/FR1352519A/en
Priority to ES286687A priority patent/ES286687A1/en
Publication of GB954720A publication Critical patent/GB954720A/en
Priority to US457835A priority patent/US3338989A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B32/00—Carbon; Compounds thereof
    • C01B32/90—Carbides
    • C01B32/914—Carbides of single elements
    • C01B32/928—Carbides of actinides
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel

Landscapes

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

Abstract

954,720. Fuel material. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 27,1963 [April 2, 1962], No. 12641/62. Heading G6C. A process for producing a uranium carbideplutonium carbide fuel material comprises taking a powder of uranium and plutonium carbides of 2 to 4 microns, containing 48 to 53 atomic per cent carbon, and less than 1% oxygen by weight, compacting the powder to form pellets, and sinteringthe pellets in an inert atmosphere. The proportion of plutonium is preferably 15 atomic per cent of the uranium, and sintering is carried out at approximately 1550‹C. in an inert atmosphere, such as argon, containing less than 10 p.p.m. oxygen. The resultant structure comprises a coherent matrix of uranium carbide, possibly containing a small proportion of plutonium carbide in solid solution, and a disperse phase of plutonium sesquicarbide. The carbide powders originate from arc melted material and may be separately powdered, or they may be in the form of a solid solution of the two carbides prior to powdering.
GB12641/62A 1962-04-02 1962-04-02 Improvements in or relating to reactor fuels Expired GB954720A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
BE630429D BE630429A (en) 1962-04-02
GB12641/62A GB954720A (en) 1962-04-02 1962-04-02 Improvements in or relating to reactor fuels
DEU9686A DE1294573B (en) 1962-04-02 1963-03-30 Method of making an enriched uranium carbide fuel material
FR929953A FR1352519A (en) 1962-04-02 1963-04-01 Fuels for nuclear reactors
ES286687A ES286687A1 (en) 1962-04-02 1963-04-02 Procedure for obtaining nuclear fuel (Machine-translation by Google Translate, not legally binding)
US457835A US3338989A (en) 1962-04-02 1965-05-21 Process for producing high density uranium carbide-plutonium carbide pellets

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB12641/62A GB954720A (en) 1962-04-02 1962-04-02 Improvements in or relating to reactor fuels

Publications (1)

Publication Number Publication Date
GB954720A true GB954720A (en) 1964-04-08

Family

ID=10008442

Family Applications (1)

Application Number Title Priority Date Filing Date
GB12641/62A Expired GB954720A (en) 1962-04-02 1962-04-02 Improvements in or relating to reactor fuels

Country Status (5)

Country Link
US (1) US3338989A (en)
BE (1) BE630429A (en)
DE (1) DE1294573B (en)
ES (1) ES286687A1 (en)
GB (1) GB954720A (en)

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AT204660B (en) * 1958-02-04 1959-08-10 Plansee Metallwerk Process for the production of fuel elements for nuclear reactors
US3162528A (en) * 1959-09-08 1964-12-22 Atomic Energy Authority Uk Production of uranium-carbon alloys
GB948791A (en) * 1960-12-02 1964-02-05 Atomic Energy Authority Uk Improvements in or relating to the production of uranium and plutonium monocarbides
US3082163A (en) * 1961-08-25 1963-03-19 Allen E Ogard Method for preparing uranium monocarbide-plutonium monocarbide solid solution
GB954821A (en) * 1962-04-02 1964-04-08 Atomic Energy Authority Uk Improvements in or relating to process for the preparation of carbide

Also Published As

Publication number Publication date
ES286687A1 (en) 1963-11-16
US3338989A (en) 1967-08-29
DE1294573B (en) 1969-05-08
BE630429A (en)

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