GB1130633A - Fuel assemblies for nuclear reactors - Google Patents

Fuel assemblies for nuclear reactors

Info

Publication number
GB1130633A
GB1130633A GB36408/65A GB3640865A GB1130633A GB 1130633 A GB1130633 A GB 1130633A GB 36408/65 A GB36408/65 A GB 36408/65A GB 3640865 A GB3640865 A GB 3640865A GB 1130633 A GB1130633 A GB 1130633A
Authority
GB
United Kingdom
Prior art keywords
fuel
rod
control
plug
assembly
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
GB36408/65A
Inventor
Alexander Walker
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.)
English Electric Co Ltd
Original Assignee
English Electric Co Ltd
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 English Electric Co Ltd filed Critical English Electric Co Ltd
Priority to GB36408/65A priority Critical patent/GB1130633A/en
Publication of GB1130633A publication Critical patent/GB1130633A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous 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
    • G21C1/10Heterogeneous 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
    • G21C1/12Heterogeneous 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
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control 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)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,130,633. Fuel elements. ENGLISH ELECTRIC CO. Ltd. 23 Aug., 1966 [24 Aug., 1965], No. 36408/65. Heading G6C. A fuel element assembly comprises an annular space through which coolant may flow over fuel bins situated in the space and a central channel through which a control-rod may move. The control-rod may be lowered to the bottom of the channel and coupled to the assembly at its lower end whereby the rod and fuel element assembly may be removed as a unit from the reactor by a lifting force applied to the top end of the control-rod. As shown, a gascooled graphite-moderated reactor has its pile cap (10), (Fig. 1, not shown), penetrated by a plurality of standpipes (11) closed by a plug (12), each standpipe having an extension 13 reaching down to a fuel channel 20 in a core formed by a top neutron shield 14 and moderator 15. Each fuel assembly comprises coaxial outer and inner stacks 30 and 31, respectively, of cylindrical graphite sleeves 30A ... 30C, 31A ... 31C, the bottom of the assembly consisting of a central boss 33 connected by a grid 35 to an outer ring 34. The conical surface of the ring 34 is supported by a seating 23D of a gag valve housing 23 fixed by a flange 23A to the core support plate 16. The grid 35 supports the lower ends of the fuel bins 36 spaced along their lengths by grids 38. The gag valve controls the flow of coolant gas from the inlet plenum 17 to the lower end of the annular space between the stacks 30, 31 and includes ports 23B in the housing 23 and ports 25A in a rotatable cylindrical valve member 25. The valve member 25 is rotated to control the gas flow by means of teeth 25C co-operating with teeth 37A on a member 37 secured to the boss 33, the arrangement being such that each time the member 37 is moved axially away from the valve member 25 and then back again it rotates the valve member by one tooth pitch. This axial movement is derived by lifting a control rod 55 supported by a chain 54 in the fuel assembly, the lower end of the control rod being formed with the male part (55B) (Fig. 1, not shown) of a bayonet fitting co-operating with a female part 60. A stem 61 extends from the part 60 to a lifting head 62 whereby after the control-rod 55 has been lowered by the chain 54 to the end of its channel and then rotated to engage the bayonet connection the fuel assembly may be either raised a small amount and then lowered to rotate the valve member 25 or it may be raised to engage the bottom of the plug (12) and the plug together with the fuel assembly then removed from the reactor. The winding mechanism (53) for the chain 54 is situated in the plug. The upper end of the fuel assembly is formed by a neutron shield plug 41 formed with helical gas passages 42.
GB36408/65A 1965-08-24 1965-08-24 Fuel assemblies for nuclear reactors Expired GB1130633A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB36408/65A GB1130633A (en) 1965-08-24 1965-08-24 Fuel assemblies for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB36408/65A GB1130633A (en) 1965-08-24 1965-08-24 Fuel assemblies for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1130633A true GB1130633A (en) 1968-10-16

Family

ID=10387860

Family Applications (1)

Application Number Title Priority Date Filing Date
GB36408/65A Expired GB1130633A (en) 1965-08-24 1965-08-24 Fuel assemblies for nuclear reactors

Country Status (1)

Country Link
GB (1) GB1130633A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2162283A1 (en) * 1971-12-09 1973-07-20 Commissariat Energie Atomique Reactor control rod - for high power, fast neutron reactor
FR2191213A1 (en) * 1972-06-29 1974-02-01 Alsacienne Atom
GB2180091A (en) * 1985-08-19 1987-03-18 English Electric Co Ltd Apparatus for use in refuelling nuclear reactors

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2162283A1 (en) * 1971-12-09 1973-07-20 Commissariat Energie Atomique Reactor control rod - for high power, fast neutron reactor
FR2191213A1 (en) * 1972-06-29 1974-02-01 Alsacienne Atom
FR2232819A2 (en) * 1972-06-29 1975-01-03 Activite Atom Avance
GB2180091A (en) * 1985-08-19 1987-03-18 English Electric Co Ltd Apparatus for use in refuelling nuclear reactors

Similar Documents

Publication Publication Date Title
GB1396767A (en) Nuclear reactor fuel assemblies
US9355747B2 (en) Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US4655995A (en) Reversible BWR fuel assembly and method of using same
US2992174A (en) Breeder-converter reactor
GB1222836A (en) Nuclear reactor core and control element arrangement
US3335060A (en) Seed-blanket neutronic reactor
GB1422796A (en) Improvements in nuclear reactors
GB1112946A (en) Improvements relating to nuclear reactors
ES8600547A1 (en) Reconstitutable fuel assembly for a nuclear reactor
US3039947A (en) Fuel elements for nuclear reactors
US3238109A (en) Fuel elements for nuclear reactors
GB1139969A (en) Fuel assemblies for nuclear reactors
GB1130633A (en) Fuel assemblies for nuclear reactors
US4717527A (en) Fuel assembly
GB1128826A (en) Fuel assembly for a nuclear reactor cooled by a liquid metal
US4770840A (en) Spectral shift light water nuclear reactor
GB1364945A (en) Nuclear fuel assembly
US3361635A (en) Nuclear reactor control rod winding arrangements
GB1373253A (en) Fuel element assemblies
GB908305A (en) Improvements in or relating to nuclear reactors
GB944699A (en) Improvements in or relating to nuclear reactors
US3085965A (en) Supports for combustible elements in atomic piles or reactors having vertical channels
GB1332773A (en) Single seed fuel module for a light water breeder reactor
US3194741A (en) Nuclear reactor fuelling apparatus
GB1186862A (en) Improvements in or relating to fast nuclear reactors