GB1431852A - Nuclear fuel and/or fertile elements and operation of a nuclear reac-or - Google Patents

Nuclear fuel and/or fertile elements and operation of a nuclear reac-or

Info

Publication number
GB1431852A
GB1431852A GB1571573A GB1571573A GB1431852A GB 1431852 A GB1431852 A GB 1431852A GB 1571573 A GB1571573 A GB 1571573A GB 1571573 A GB1571573 A GB 1571573A GB 1431852 A GB1431852 A GB 1431852A
Authority
GB
United Kingdom
Prior art keywords
particles
carbide
oxide
nuclear fuel
fuel
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
GB1571573A
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.)
Forschungszentrum Juelich GmbH
Original Assignee
Kernforschungsanlage Juelich GmbH
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 DE19722215907 external-priority patent/DE2215907C3/en
Application filed by Kernforschungsanlage Juelich GmbH filed Critical Kernforschungsanlage Juelich GmbH
Publication of GB1431852A publication Critical patent/GB1431852A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (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

1431852 Nuclear fuel KERNFORSCHUNGSANLAGE JULICH GmbH 2 April 1973 [1 April 1972] 15715/73 Heading G6C Nuclear fuel and/or fertile material comprises coated particles of a mixture of a fissile or fertile metal oxide and a fissile or fertile metal carbide, for example mixtures of oxides and carbides of U, U-Th, or U-Pu. The proportion of carbide in the mixture (e.g. 3-20%) is such that during burn-up sufficient carbide remains to react with the oxygen produced from the oxide. The invention reduces the disadvantageous formation of CO by reaction of this oxygen with the carbon in the particle coating, which may be pyrolytic carbon and/or silicon carbide. The fuel may be made by hydrolysing and peptizing a nuclear fuel oxide to form a sol, mixing the sol with carbon black, forming spherical gel particles, sintering in a reducing atmosphere, and then coating the particles. Alternatively, the oxide powder may be mixed with powdered carbon or graphite and a binder, e.g. aluminium stearate, and formed into spherical particles which are sintered and coated. A layer containing oxide but no carbide may be provided between the core and the coating. Fuel elements may be formed by introducing the particles into a metal or graphite casing or into a graphite matrix, and are suitable for use in a high temperature or fast breeder reactor.
GB1571573A 1972-04-01 1973-04-02 Nuclear fuel and/or fertile elements and operation of a nuclear reac-or Expired GB1431852A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19722215907 DE2215907C3 (en) 1972-04-01 Fuel and / or breeding elements for nuclear reactors and processes for producing fuel and / or breeding elements

Publications (1)

Publication Number Publication Date
GB1431852A true GB1431852A (en) 1976-04-14

Family

ID=5840791

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1571573A Expired GB1431852A (en) 1972-04-01 1973-04-02 Nuclear fuel and/or fertile elements and operation of a nuclear reac-or

Country Status (3)

Country Link
JP (1) JPS6034078B2 (en)
FR (1) FR2178949B1 (en)
GB (1) GB1431852A (en)

Also Published As

Publication number Publication date
DE2215907B2 (en) 1976-07-01
FR2178949B1 (en) 1977-08-05
DE2215907A1 (en) 1973-10-18
JPS4913599A (en) 1974-02-06
FR2178949A1 (en) 1973-11-16
JPS6034078B2 (en) 1985-08-06

Similar Documents

Publication Publication Date Title
GB952090A (en) Nuclear fuel element and process of making the same
US3504058A (en) Process for manufacturing sintered pellets of nuclear fuel
GB1490391A (en) Nuclear fuel particles
CA1107054A (en) Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets
GB1289940A (en)
GB1388965A (en) Nuclear fuel for high temperature gas-cooled reactors
US3536793A (en) Method of making porous metal carbide agglomerates
GB1107300A (en) Moderator-nuclear fuel element
GB1431852A (en) Nuclear fuel and/or fertile elements and operation of a nuclear reac-or
GB1034505A (en) Improvements in or relating to sintered uranium-plutonium compounds
GB1334391A (en) Nuclear fuels
GB1411024A (en) Method of fabricating porous cermets containing a fissile material
US3205174A (en) Nuclear fuel materials including vitreous phase
JPH041594A (en) Nuclear fuel pellet and its manufacture
US3378498A (en) Process for diffusing metal into a refractory or ceramic oxide using a nitrate promoter
GB1371699A (en) Fission product retaining nuclear reactor fuel
ES309178A1 (en) Method of preparation of mixed oxides of actinides
GB918044A (en) Production of nuclear fuels, moderators or control members
Horsley Improvements in or relating to nuclear reactor fuel bodies
GB1437691A (en) Method of mahuffacturing cermets from isotopic sources and products obtained thereby
GB1233331A (en)
Mardon Powder metallurgy techniques in nuclear technology
US7012168B1 (en) Boron-based containment matrix for the storage or transmutation of long-life radioactive elements
GB1375575A (en) Improvements in or relating to encapsulated or clad nuclear fuel bodies
GB1468261A (en) Nuclear fuel particles for use in the manufacture of nuclear fuel bodies

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee