GB882633A - Improvements relating to devices for supporting fuel elements in a nuclear reactor - Google Patents

Improvements relating to devices for supporting fuel elements in a nuclear reactor

Info

Publication number
GB882633A
GB882633A GB21306/57A GB2130657A GB882633A GB 882633 A GB882633 A GB 882633A GB 21306/57 A GB21306/57 A GB 21306/57A GB 2130657 A GB2130657 A GB 2130657A GB 882633 A GB882633 A GB 882633A
Authority
GB
United Kingdom
Prior art keywords
sleeve
latches
ram
moved
seating
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
GB21306/57A
Inventor
John Anthony Collis-Smith
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 GB21306/57A priority Critical patent/GB882633A/en
Publication of GB882633A publication Critical patent/GB882633A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/06Means for locating or supporting 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)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)

Abstract

882,633. Reactors; handling nuclear fuel elements. ENGLISH ELECTRIC CO. Ltd. Oct. 3 1958 [July 5, 1957], No. 21306/57. Class 39(4) A sleeve 10 for removably supporting a fuel element 14 in a channel 17 in a reactor moderator structure has four circumferentiallyspeced latches 11 gravity-biased to the vertical position but movable by rams (Figs. 3, 5) to the position shown to rest on the lower face of a groove 15 formed in a support tube 16. The loading ram 33, Fig. 3, comprises a head 30 on which is slidably mounted an annular sleeve 31 biased by a spring 32. On loading a fuel element the sleeve 10 rests in seating 35 and the sleeve 31 holds the latches 11- horizontal, the latches being deflected against the bias of spring 32 as they ride up the tapered surface 16a of the tube 16. On arrival at the groove 15 the spring moves the latches horizontal whereupon the ram 33 may be withdrawn. An unloading ram 41, Fig. 4, comprises a head 40 having a seating 43 which is moved up into the channel to engage the sleeve 10 and lift it to permit the latches 11 to drop to the vertical position whereupon the ram and sleeve may be withdrawn. A combined loading and unloading ram 50, Fig. 5, comprises an upper member 51 rigidly supporting a central bush 53 having a seating 54 to receive the sleeve 10. A cup member 55 is slidably mounted on the bush 53 and is biased upwardly to the position shown by springs 56 acting against the heads of bolts 58 attached to the member 55, the latter then holding the latches 11 horizontal. A sleeve 62 having three angularly-spaced lugs 64 engaging the bottom of the member 55 is slidably mounted in the bush 53 and may be moved downwards against the bias of a spring 63 by a piston 60 when compressed gas is supplied through a duct 81 to the upper end of a cylinder 59. The upper member 51 is slidably connected to a lower ram member 52 by a piston 74 rigid with the member 51 and having its motion restricted, by a flanged ring 76 rigid with the member 52. In a loading operation the gas is supplied at such pressure to the cylinder bore 75 that the member 51 is moved away from the member 52 to permit a normally-open micro switch 82 to close and give an indication, which indication would be cancelled if the fuel element should meet an obstruction. This gas pressure is insufficient to move down the piston 60 whereby when the latches 11 arrive at the groove 15 they are moved outwardly by the springs 56. To unload a fuel element a higher gas pressure is used so that the cup member 55 is moved downwards whereupon when the sleeve 10 is lifted by the seating 54 the latches 11 drop down. If the sleeve 10 should not follow the ram it may be positively removed by increasing the gas pressure still further so that piston 60 moves further down to take up a lost-motion connection between slots 71 in the lugs 64 and pins 70 of links 69. The links 69 are connected to levers 66 pivoted on the bush 53 and is biased by springs 72 to the position shown, the levers being moved by the high gas pressure to engage an annular groove 10a in the sleeve.
GB21306/57A 1957-07-05 1957-07-05 Improvements relating to devices for supporting fuel elements in a nuclear reactor Expired GB882633A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB21306/57A GB882633A (en) 1957-07-05 1957-07-05 Improvements relating to devices for supporting fuel elements in a nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB21306/57A GB882633A (en) 1957-07-05 1957-07-05 Improvements relating to devices for supporting fuel elements in a nuclear reactor

Publications (1)

Publication Number Publication Date
GB882633A true GB882633A (en) 1961-11-15

Family

ID=10160653

Family Applications (1)

Application Number Title Priority Date Filing Date
GB21306/57A Expired GB882633A (en) 1957-07-05 1957-07-05 Improvements relating to devices for supporting fuel elements in a nuclear reactor

Country Status (1)

Country Link
GB (1) GB882633A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1206097B (en) * 1962-07-24 1965-12-02 Interatom Coupling for fuel and / or moderator elements of a nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1206097B (en) * 1962-07-24 1965-12-02 Interatom Coupling for fuel and / or moderator elements of a nuclear reactor

Similar Documents

Publication Publication Date Title
US3607639A (en) Fuel assembly for nuclear reactors
GB1432732A (en) Hoist for use with nuclear reactors
GB854882A (en) Improvements relating to fuel elements for nuclear reactors and to nuclear reactors using such elements
JP2553333B2 (en) Fuel assembly
NL282482A (en)
CN103474112A (en) Reactor internal hoisting tool
GB834365A (en) Improvements in or relating to control rod assemblies for nuclear reactors
US4268357A (en) Positive lock holddown device
GB830422A (en) Improvements in or relating to plugs or closures
GB882633A (en) Improvements relating to devices for supporting fuel elements in a nuclear reactor
GB1190603A (en) Improvements in or relating to Core Element Handling Systems for Nuclear Reactors.
GB1018561A (en) Improvements in or relating to apparatus for charging aerosol containers with propellant
EP0268494A3 (en) Gripper assembly for inserting and removing burnable absorber rods and thimble plugs in a nuclear reactor fuel assembly
GB1446154A (en) Gripper mechanism for control and shut-down rods in a nuclear reactor
GB893244A (en) Improvements in apparatus for loading and unloading nuclear fuel elements
GB871746A (en) Telescoping fuel element assembly for a nuclear reactor and operating means
US3872565A (en) Reactor vessel seal service fixture
US3766006A (en) Rapidly refuelable nuclear reactor
GB964051A (en) Improved mechanism for transferring articles
CN221139098U (en) Up-down combined environment protection tray
CN216896068U (en) Static valve core copper ring positioning mechanism
CN214725658U (en) A mould for new energy automobile accessories
GB854144A (en) Improvements in or relating to nuclear reactors
GB908059A (en) Improvements relating to safety devices for nuclear reactors
CN211626830U (en) Helium leak detection prebuckling feeding device pushing and aligning mechanism