GB1268186A - Improvements in or relating to nuclear reactor fuel elements - Google Patents

Improvements in or relating to nuclear reactor fuel elements

Info

Publication number
GB1268186A
GB1268186A GB33902/68A GB3390268A GB1268186A GB 1268186 A GB1268186 A GB 1268186A GB 33902/68 A GB33902/68 A GB 33902/68A GB 3390268 A GB3390268 A GB 3390268A GB 1268186 A GB1268186 A GB 1268186A
Authority
GB
United Kingdom
Prior art keywords
fuel
interlayers
fissile
sheathing
interlayer
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
GB33902/68A
Inventor
David Lees Linning
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
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to JP6931964A priority Critical patent/JPS5322239B1/ja
Priority to DE1921203A priority patent/DE1921203C3/en
Priority to FR6913342A priority patent/FR2009838A2/en
Publication of GB1268186A publication Critical patent/GB1268186A/en
Expired legal-status Critical Current

Links

Classifications

    • HELECTRICITY
    • H01ELECTRIC ELEMENTS
    • H01BCABLES; CONDUCTORS; INSULATORS; SELECTION OF MATERIALS FOR THEIR CONDUCTIVE, INSULATING OR DIELECTRIC PROPERTIES
    • H01B1/00Conductors or conductive bodies characterised by the conductive materials; Selection of materials as conductors
    • H01B1/20Conductive material dispersed in non-conductive organic material
    • H01B1/24Conductive material dispersed in non-conductive organic material the conductive material comprising carbon-silicon compounds, carbon or silicon
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/20Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,268,186. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 21 April, 1969 [26 April, 1968; 16 July, 1968], Nos. 20041/68 and 33902/68. Addition to 1,174,575. Heading G6C. A fuel element of the type specified in the main parent Specification is, in one feature of the invention, in the form of an elongate fuel member and its metallic sheathing includes both internal and external sheathing between which the fuel is disposed, the fuel member thus being of the tubular type and there being an interlayer disposed between and directly contacting the fuel and each of the internal and external sheathing. The interlayers are preferably of a ceramic compound of U of either natural or depleted fissile isotopic abundance, and the fuel is a ceramic compound of Pu, a mixture of ceramic compounds of U and Pu, or a fissile-enriched ceramic compound of U. The interlayers may be in pellet form with the fuel in the form of vibro-compacted ceramic particles, or the interlayers may be of vibrocompacted ceramic particles and the fuel in pellet form, or the interlayers and the fuel may all be in pellet form. Where the fuel is of pellet form, it may be in two annular portions with an annular gap therebetween to provide a fission product reservoir and enable gaseous fission products the better to pass to a gaseous fission product plenum at one end of the fuel element or to gaseous fission product venting means, and also to assist in providing voidage for the accommodation of irradiation-induced swelling. The fuel density is preferably less than 85% of maximum theoretical density. In one embodiment, each fuel pellet has at least three radial ribs extending from its inner and outer surfaces to contact the sheaths, the part-annular spaces between the ribs being occupied by vibrocompacted UO 2 to form the interlayers. Where the fuel is of carbide compounds, a thin, non- fissile, non-fertile compatibility layer is provided between each interlayer and the respective sheathing over at least that axial region of the fuel zone of the fuel member which is subjected to maximum burn-up in operation. Suitable materials for the compatibility layer include MgO, TiO 2 and ZrO 2 . This layer may be applied by spraying or dipping, those parts outside the axial region of maximum burn-up not requiring the layer being masked. Where the fuel member is not of the tubular type, as according to another feature of the invention, it has its interlayer of UC of natural or depleted fissile isotopic abundance, its fuel of PuC, mixed PuC and UC, or enriched UC, and there is additionally provided between the interlayer and the sheathing, a thin compatibility layer of non-fissile, non-fertile material, such as is described with reference to the firstmentioned feature.
GB33902/68A 1965-12-23 1968-04-26 Improvements in or relating to nuclear reactor fuel elements Expired GB1268186A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
JP6931964A JPS5322239B1 (en) 1968-04-26 1969-04-24
DE1921203A DE1921203C3 (en) 1965-12-23 1969-04-25 Fuel assembly for a nuclear reactor
FR6913342A FR2009838A2 (en) 1968-04-26 1969-04-25 Fuel cartridges for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2004168 1968-04-26

Publications (1)

Publication Number Publication Date
GB1268186A true GB1268186A (en) 1972-03-22

Family

ID=10139371

Family Applications (1)

Application Number Title Priority Date Filing Date
GB33902/68A Expired GB1268186A (en) 1965-12-23 1968-04-26 Improvements in or relating to nuclear reactor fuel elements

Country Status (1)

Country Link
GB (1) GB1268186A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102640230A (en) * 2009-10-08 2012-08-15 法国原子能及替代能源委员会 Body for a nuclear fuel assembly, and nuclear fuel assembly comprising such a body

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102640230A (en) * 2009-10-08 2012-08-15 法国原子能及替代能源委员会 Body for a nuclear fuel assembly, and nuclear fuel assembly comprising such a body
US9589681B2 (en) 2009-10-08 2017-03-07 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear fuel assembly body and a nuclear fuel assembly with such a body

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