GB1265964A - - Google Patents

Info

Publication number
GB1265964A
GB1265964A GB1706268A GB1265964DA GB1265964A GB 1265964 A GB1265964 A GB 1265964A GB 1706268 A GB1706268 A GB 1706268A GB 1265964D A GB1265964D A GB 1265964DA GB 1265964 A GB1265964 A GB 1265964A
Authority
GB
United Kingdom
Prior art keywords
fuel
wires
assembly
sleeve
core
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
GB1706268A
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 filed Critical
Publication of GB1265964A publication Critical patent/GB1265964A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/06—Means for locating or supporting fuel elements
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear 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)

Abstract

1,265,964. Fuel elements. BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd. 9 April, 1969 [9 April, 1968], No. 17062/68. Heading G6C. A sleeved fuel element assembly support arrangement comprises a triple armed support member 21 which carries the fuel assembly 10, and three Zr-alloy wires 22 extending vertically outside the assembly, being attached at their lower ends to the arms of the support member 21 and at their upper ends to lifting means such that the assembly may be lifted out of a fuel channel 11 extending through a reactor core 12. The lifting means comprises a steel carrier tube 13 which is carried by a plug 14 within a standpipe 15 passing through the top cap 16 of the concrete pressure vessel housing the reactor. The fuel assembly 10 includes a graphite sleeve 17 which contains for example, a stack of sleeved layers of fuel pins (generally referenced 18), a reflector 19 and a spiral neutron plug 20. The wires 22 extend through grooves formed in the outer wall of the sleeve 17 to an anchorage point in the carrier tube 13. The grooves are shaped so that their radially outermost width is less than the diameter of the wires 22, which are thus trapped in position within the grooves. The length of the wires 22 is such that they are slack when the fuel assembly 10 is in position within the fuel channel 11. Coolant gas is fed to the underside of the core 12 and some of this passes around the core 12 and into the fuel channel 11 through an opening 25. This gas passes down the outside of the sleeve 17, thereby cooling the moderator of the core 12, to rejoin the remainder of the coolant gas flow and pass up the fuel assembly 10 within the sleeve 17. In order to refuel the reactor, the plug 14 is withdrawn through the standpipe 15 and once the slack in the wires 22 has been taken up, the fuel assembly 10 is lifted out of the channel 11. The provision of a spherical rocker on the support member 21 allows the fuel assembly 10 to take up the position in which the three wires 22 are equally loaded.
GB1706268A 1968-04-09 1968-04-09 Expired GB1265964A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1706268 1968-04-09

Publications (1)

Publication Number Publication Date
GB1265964A true GB1265964A (en) 1972-03-08

Family

ID=10088582

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1706268A Expired GB1265964A (en) 1968-04-09 1968-04-09

Country Status (1)

Country Link
GB (1) GB1265964A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4268357A (en) * 1978-11-24 1981-05-19 Combustion Engineering, Inc. Positive lock holddown device
GB2206989A (en) * 1987-07-16 1989-01-18 British Nuclear Fuels Plc Nuclear reactor fuel assemblies

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4268357A (en) * 1978-11-24 1981-05-19 Combustion Engineering, Inc. Positive lock holddown device
GB2206989A (en) * 1987-07-16 1989-01-18 British Nuclear Fuels Plc Nuclear reactor fuel assemblies
GB2206989B (en) * 1987-07-16 1990-03-07 British Nuclear Fuels Plc Nuclear reactor fuel assemblies

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PLNP Patent lapsed through nonpayment of renewal fees