[go: up one dir, main page]

GB1162578A - Improvements in and relating to a Nuclear Reactor Fuel Element Assembly - Google Patents

Improvements in and relating to a Nuclear Reactor Fuel Element Assembly

Info

Publication number
GB1162578A
GB1162578A GB31641/67A GB3164167A GB1162578A GB 1162578 A GB1162578 A GB 1162578A GB 31641/67 A GB31641/67 A GB 31641/67A GB 3164167 A GB3164167 A GB 3164167A GB 1162578 A GB1162578 A GB 1162578A
Authority
GB
United Kingdom
Prior art keywords
fuel
sleeve
pencils
tie
rods
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
GB31641/67A
Inventor
Jean-Pierre Peyrot
Paul Thome
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB1162578A publication Critical patent/GB1162578A/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
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,162,578. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 10 July, 1967 [12 Aug., 1966]. No. 31641/67. Heading G6C. A transverse support grid for a cluster-type fuel element assembly is formed of spigot rings 5 which fit over and are secured to the upper ends of the fuel pencils 1 and coupling members 11 which connect each ring 5 to at least one adjacent ring and have internal ducts 12 for providing communication between spaces 4 between the cans 2 and the fuel 3 at the upper ends of the fuel pencils 1. A number of solid discs 13 are disposed around the periphery of the support grid and engage in recesses 15 in tie-rods 14. The tie-rods 14 are coupled to each other by means of a metallic sleeve 16 welded to the tie-rods at 17 and surrounded by an outer metallic sleeve 18. The two sleeves 16, 18 are coupled together at one end by means of a circular collar 19 and at the other end by means of a circular collar 46. At this latter end, the sleeve 18 terminates short of the sleeve 16. The ends of each tie-rod 14 are so shaped (Fig. 3, not shown) as to provide a male portion and a female portion, with the result that the tierods of two fuel element assemblies which are superposed in a nuclear reactor fuel channel can be interengaged and the fuel pencils of each cluster axially positioned in the line of extension of each other. The spigot rings 5 are closed at the top by caps 8. The ducts 12 of the coupling members 11 and a number of peripheral fuel pencils 1 are connected to funnel-type components 24 in each of which is formed an axial bore 25 closed at the top by a cap 26. Each component 24 has an arm 27 engaging in a recess 28 of the circular collar 19 and provided with an internal duct 29 through which fission product gases released from the fuel pencils 1 are conveyed to an expansion chamber 30 located between the two sleeves 16, 18. The chamber 30 is delimited by a casing 31 applied against the outer sleeve 18 and a casing 32 separated from the inner sleeve 16 by a layer 34 of heat-insulating material. The two casings 31, 32 are sufficiently thin to deform under the effect of variations of pressure. In the position shown in Fig. 2, the volume of chamber 30 is a maximum as during normal operation. In the event of a shut-down, the two casings 31, 32 can contract and thereby reduce the volume of chamber 30. The fuel cluster is completed at the lower end of the fuel pencils by a member which permits of free expansion of the pencils. The cans 2 are sealed at their lower end by end caps 35 in each of which is formed a blind-end bore 36 in which is mounted a ball 37 and a stud 38. After insertion through seals 39, the studs are secured to a simple grid 40, the ends 41 of which are fitted in a channel 42 formed at the base of the tie-rods 14. Each fuel pencil 1 is divided at the centre by a plug provided with radial fins for the purpose of bracing the fuel cluster. The collar 46 formed either of graphite or silica is radially proud of the sleeve 18 and is applied against the wall of the fuel channel to prevent any coolant flowing between the channel wall and the sleeve 18. The cans 2 may be formed of Zr alloy, Be, Si, graphite or SiC whilst the tie-rods 14 may be formed of impregnated graphite, Si or SiC and the support grids and sleeves 16, 18 of Nb, Zr alloy or steel.
GB31641/67A 1966-08-12 1967-07-10 Improvements in and relating to a Nuclear Reactor Fuel Element Assembly Expired GB1162578A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR73050 1966-08-12

Publications (1)

Publication Number Publication Date
GB1162578A true GB1162578A (en) 1969-08-27

Family

ID=8615385

Family Applications (1)

Application Number Title Priority Date Filing Date
GB31641/67A Expired GB1162578A (en) 1966-08-12 1967-07-10 Improvements in and relating to a Nuclear Reactor Fuel Element Assembly

Country Status (6)

Country Link
BE (1) BE700223A (en)
ES (1) ES344070A1 (en)
FR (1) FR1604122A (en)
GB (1) GB1162578A (en)
LU (1) LU54284A1 (en)
NL (1) NL6710982A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2163888A (en) * 1984-08-30 1986-03-05 Atomic Energy Authority Uk Fission gas plenum chamber for nuclear fuel element sub-assembly
GB2163889A (en) * 1984-08-30 1986-03-05 Atomic Energy Authority Uk Fuel assembly

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2163888A (en) * 1984-08-30 1986-03-05 Atomic Energy Authority Uk Fission gas plenum chamber for nuclear fuel element sub-assembly
GB2163889A (en) * 1984-08-30 1986-03-05 Atomic Energy Authority Uk Fuel assembly

Also Published As

Publication number Publication date
NL6710982A (en) 1968-02-13
FR1604122A (en) 1971-07-12
LU54284A1 (en) 1967-10-09
BE700223A (en) 1967-12-01
ES344070A1 (en) 1968-12-16

Similar Documents

Publication Publication Date Title
US3089830A (en) Method of making a compartmented fuel element for a nuclear reactor
GB1537225A (en) Fast neutron nuclear reactor
GB1389174A (en) Nuclear reactor
GB852957A (en) Improvements in or relating to cooling systems for nuclear reactors
GB845804A (en) Improvements in or relating to elements of fissionable material
GB1382392A (en) Removable diagrid for supporting the fuel assemblies of a nuclear reactor
GB1366621A (en) Device for permitting or facilitating the handling of the elements which form a nuclear reactor core
GB1162578A (en) Improvements in and relating to a Nuclear Reactor Fuel Element Assembly
GB847636A (en) Improvements in or relating to nuclear reactor refuelling devices
US3206369A (en) Fuel elements for nuclear reactors
GB1057958A (en) Improvements in braces for fuel element clusters
GB1373253A (en) Fuel element assemblies
US4188038A (en) Seal arrangement for intersecting conduits
GB907344A (en) Improvements in methods and devices for securing fuel elements in nuclear reactor tubular channels
GB1110787A (en) Fluid seals
US3243353A (en) Fluid-tight access means for a nuclear reactor
GB951165A (en) Improvements in or relating to nuclear reactors
US3266997A (en) Means for supporting nuclear fuel components in moderator channel
GB884855A (en) Improvements in or relating to nuclear reactor shielding
GB1044450A (en) Fuel handling device for nuclear reactor
GB1393038A (en) Fuel element for a nuclear reactor
GB1130655A (en) Improvements in and relating to fuel element assemblies
GB1025939A (en) Improvements in devices for securing the feet of nuclear fuel elements
GB879902A (en) Improvements in or relating to nuclear reactors
GB1198001A (en) Nuclear Reactors

Legal Events

Date Code Title Description
PS Patent sealed
PLNP Patent lapsed through nonpayment of renewal fees