GB932464A - Improvements in or relating to nuclear fuel elements - Google Patents

Improvements in or relating to nuclear fuel elements

Info

Publication number
GB932464A
GB932464A GB36927/60A GB3692760A GB932464A GB 932464 A GB932464 A GB 932464A GB 36927/60 A GB36927/60 A GB 36927/60A GB 3692760 A GB3692760 A GB 3692760A GB 932464 A GB932464 A GB 932464A
Authority
GB
United Kingdom
Prior art keywords
fuel
strips
troughs
oct
thickness
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
GB36927/60A
Inventor
Peter Waine
James Duncan Waters
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 GB36927/60A priority Critical patent/GB932464A/en
Priority to FR876674A priority patent/FR1304319A/en
Priority to DE19611439776 priority patent/DE1439776A1/en
Priority to ES271466A priority patent/ES271466A1/en
Publication of GB932464A publication Critical patent/GB932464A/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
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)

Abstract

932,464. Nuclear fuel elements. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Oct. 11, 1961 [Oct. 27, 1960], No. 36927/60. Class 39 (4). A rod cluster fuel assembly support structure 4 of openwork construction is fabricated from strips 5, e.g. of stainless steel 0.01 inch thick, with transverse troughs 6 at intervals and assembled with the lengths of the strips 5 intermediate the troughs 6 secured together at their centres by resistance welds 7 to form webs 40 of double thickness, the troughs 6 coming together to define a number of spaced openings 8 bounded by a single thickness of strip material for receiving the fuel rods in the cluster. Flanged webs 25 connect the structure 4 with a U-section, annular support 26 (0.016 inch thickness) disposed between upper and lower graphite sleeves 27 inside a tubular housing 3 of graphite. Each fuel rod comprises a stack of sintered UO 2 fuel pellets in a tubular, stainless steel sheath 10, the ends of which carry collars and the weight of the fuel rods is taken on the lower collars by the upper edges of the strips 5. The fuel pellets are spaced from the caps sealing the ends of the sheaths 10 by heat-insulating plugs 12 of sintered alumina.
GB36927/60A 1960-10-27 1960-10-27 Improvements in or relating to nuclear fuel elements Expired GB932464A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
GB36927/60A GB932464A (en) 1960-10-27 1960-10-27 Improvements in or relating to nuclear fuel elements
FR876674A FR1304319A (en) 1960-10-27 1961-10-21 Nuclear cartridges
DE19611439776 DE1439776A1 (en) 1960-10-27 1961-10-23 Holding arrangement for nuclear reactor fuel elements
ES271466A ES271466A1 (en) 1960-10-27 1961-10-24 Improvements in nuclear combustible sets (Machine-translation by Google Translate, not legally binding)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB36927/60A GB932464A (en) 1960-10-27 1960-10-27 Improvements in or relating to nuclear fuel elements

Publications (1)

Publication Number Publication Date
GB932464A true GB932464A (en) 1963-07-24

Family

ID=10392314

Family Applications (1)

Application Number Title Priority Date Filing Date
GB36927/60A Expired GB932464A (en) 1960-10-27 1960-10-27 Improvements in or relating to nuclear fuel elements

Country Status (3)

Country Link
DE (1) DE1439776A1 (en)
ES (1) ES271466A1 (en)
GB (1) GB932464A (en)

Also Published As

Publication number Publication date
DE1439776A1 (en) 1969-03-13
ES271466A1 (en) 1962-07-01

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