GB991258A - Nuclear reactor fuel elements - Google Patents

Nuclear reactor fuel elements

Info

Publication number
GB991258A
GB991258A GB21432/62A GB2143262A GB991258A GB 991258 A GB991258 A GB 991258A GB 21432/62 A GB21432/62 A GB 21432/62A GB 2143262 A GB2143262 A GB 2143262A GB 991258 A GB991258 A GB 991258A
Authority
GB
United Kingdom
Prior art keywords
members
fuel
graphite
sheaths
plate
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
GB21432/62A
Inventor
James Douglas Thorn
Ronald Scott Challender
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 GB21432/62A priority Critical patent/GB991258A/en
Priority to FR936828A priority patent/FR1365533A/en
Publication of GB991258A publication Critical patent/GB991258A/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
    • G21C3/3213Means for the storage or removal of fission gases
    • 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)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

991,258. Nuclear fuel elements. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. May 23, 1963 [June 4, 1962], No. 21432/62. Heading G6C. A cluster of fuel members having sheaths of moderating material, e.g. graphite, in contact with one another except at voids which permit coolant flow over the members, is supported between end plates, each of the sheaths consisting of separate lengths the ends of which are sealed into perforated support grids. The junction between upper and lower sections 3, 4 of a fuel member is shown in Fig. 7, each section comprising a series of subsection 3a arranged end-to-end and enclosed by graphite sheaths 10, 11. Each sub-section 3a comprises tubular fissile members 5 mounted on a graphite spine 6 and enclosed in a graphite sleeve 8. The sub-sections 3a comprises tubular fissile members 5 mounted on a graphite spine 6 and enclosed in a graphite sleeve 8. The sub-sections 3a interconnect by means of a spigot 14 on the upper end of each spine 6 engaging with a socket 15 of the lower end of each sleeve 8. The ends of the sheaths 10, 11 are of reduced section to form spigots 19 which engage with sockets 20 in a graphite support grid 2. The junctions between the spines 6 and sleeves 8, between adjacent sleeves 8, and between sheaths 10, 11 and the grid 2 are high temperature bonded to provide a firm and rigid joint between the sections 3, 4. Referring now to Fig. 6, the upper end plate 12 has on its underside three screw-threaded sockets 22 for the location of the upper ends of fuel members 1a and seventeen sockets 23 for the location of the upper ends of the remaining fuel members 1. Each fuel member 1a has a metal end cap 24 with an extension 25 carrying a flexible diaphragm 26. A screw-threaded collar 29 engages each socket 22 to clamp the diaphragm 26 to the plate 12,the collar 29 being countersunk to allow flexing of the diaphragm whereby differential expansion of the fuel members 1a can be accommodated. To accommodate thermal expansion of the fuel members 1, the upper sections 3 have graphite extensions 31 which slidably engage the sockets 23. The lower ends of the fuel members 1, 1a are located in the lower end plate 13 by countersunk apertures 34 and secured by screw bolts 35 as shown in Fig. 8. The lower sleeves 8 are secured in the lower ends of the sheaths 11 by screw threaded collars 36 and have tubular extensions 37 to which are bonded stainless steel tubular end caps 38 screw threaded to engage the bolts 35. Each of the fuel members 1 has a resiliently flexible bellows 39 interposed between the extension 37 and the end cap 38 so that they are merely laterally located by the apertures 34 and end caps 38 whilst the members 1a are rigidly secured to the lower end plate 13. Fission products can be purged from the fuel members by a stream of coolant gas drawn through apertures 58 in the sheaths 11, upwardly between the sleeves 8 and the sheathes 11, 10, thence downwardly via the interfaces sleeves 8 tubular members 5 and tubular members 5/spines 6, and out through a nozzle 46b. Side apertures 53 in a conical member 46 secured to the underside of plate 13 provide access for cooling fluid which flows upwardly through passageways 52 to the passageways between the fuel members 1, 1a and the apertures 33 in the plate 12. For charging and discharging the cluster into and from a reactor core, a central bore 32 provides access for a lifting grap to a lifting attachment 55 secured to the plate 13, the bore 32 normally being closed by a plug 56 to which is attached an elongate graphite rod 57. Specification 967,203 is referred to.
GB21432/62A 1962-06-04 1962-06-04 Nuclear reactor fuel elements Expired GB991258A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB21432/62A GB991258A (en) 1962-06-04 1962-06-04 Nuclear reactor fuel elements
FR936828A FR1365533A (en) 1962-06-04 1963-05-31 Fuel cartridges for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB21432/62A GB991258A (en) 1962-06-04 1962-06-04 Nuclear reactor fuel elements

Publications (1)

Publication Number Publication Date
GB991258A true GB991258A (en) 1965-05-05

Family

ID=10162857

Family Applications (1)

Application Number Title Priority Date Filing Date
GB21432/62A Expired GB991258A (en) 1962-06-04 1962-06-04 Nuclear reactor fuel elements

Country Status (1)

Country Link
GB (1) GB991258A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1539810B1 (en) * 1965-10-08 1970-04-09 Commissariat Energie Atomique Metal-cooled, fast nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1539810B1 (en) * 1965-10-08 1970-04-09 Commissariat Energie Atomique Metal-cooled, fast nuclear reactor

Similar Documents

Publication Publication Date Title
GB873073A (en) Improvements in or relating to fuel elements for nuclear reactors
US3389056A (en) Fuel assemblies
GB973701A (en) Improvements in or relating to exchange processes
ES386973A1 (en) Flow deflector for nuclear fuel element assemblies
GB847124A (en) Improvements in or relating to fuel elements for nuclear reactors
GB1139969A (en) Fuel assemblies for nuclear reactors
GB1085700A (en) Fuel assembly for nuclear reactors
GB991258A (en) Nuclear reactor fuel elements
GB1128826A (en) Fuel assembly for a nuclear reactor cooled by a liquid metal
US3247076A (en) Fuel elements for nuclear reactors with lateral support means
GB1122272A (en) Improvements in or relating to nuclear reactors
GB1169868A (en) Nuclear Fuel Assembly
GB908305A (en) Improvements in or relating to nuclear reactors
GB990429A (en) Nuclear reactors
US3206369A (en) Fuel elements for nuclear reactors
GB873074A (en) Improvements in or relating to temperature control means for nuclear reactors
US3284315A (en) Nuclear reactor fuel element assembly
GB1519546A (en) Nuclear reactor
GB1134698A (en) Improvements relating to nuclear reactors
US3663365A (en) Nuclear reactor fuel element assemblies
GB1023133A (en) Improvements in or relating to fuel elements for nuclear reactors
GB1190409A (en) Nuclear Reactor Fuel Bundle
ES281689U (en) Fuel-element bundle for a nuclear reactor.
GB928394A (en) Improvements in or relating to fuel element assemblies
GB964628A (en) Supporting-post for the solid moderator pile of a nuclear reactor