GB1083460A - Improvements relating to fuelling machines for nuclear reactors - Google Patents

Improvements relating to fuelling machines for nuclear reactors

Info

Publication number
GB1083460A
GB1083460A GB4533/63A GB453363A GB1083460A GB 1083460 A GB1083460 A GB 1083460A GB 4533/63 A GB4533/63 A GB 4533/63A GB 453363 A GB453363 A GB 453363A GB 1083460 A GB1083460 A GB 1083460A
Authority
GB
United Kingdom
Prior art keywords
shaft
teeth
winches
platform
gear
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
GB4533/63A
Inventor
Derek Collier
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.)
WFEL Ltd
Original Assignee
Fairey Engineering 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 Fairey Engineering Ltd filed Critical Fairey Engineering Ltd
Priority to GB4533/63A priority Critical patent/GB1083460A/en
Publication of GB1083460A publication Critical patent/GB1083460A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control 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
    • G21C7/12—Means for moving control elements to desired position
    • 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
    • G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
    • 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
    • G21C19/11—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with revolving coupling elements, e.g. socket coupling
    • 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
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Gear Transmission (AREA)

Abstract

1,083,460. Winches. FAIREY ENGINEERING Ltd. May 4, 1964 [Feb. 4, 1963], No. 4533/63. Heading B8B. [Also in Division G6] A machine 10 for transferring nuclear reactor fuel elements or control rods by means of winches and movable over the reactor charge floor on a chassis as disclosed in Specification 9794/63 for alignment with a selected standpipe comprises a mushroom-shaped pressure shell 10A having a head 13. A platform 17 carries three similar winches 18 any one of which may be selected and brought to a common operating station by rotating the platform through its toothed periphery 16. An electric motor 15 for alternatively driving the platform 17 or the selected winch 18 transmits its drive through a gear-box 39 to a vertical shaft 12 axially movable and rotatable in a housing 20. Axial movement of the shaft 12 is obtained through an hydraulic jack 33 operating a rod 40 through a lever 35, the rod abutting the lower end of the shaft. The upper end of the shaft carries two ring members 45, 46 having internal teeth 47, Fig. 4, such that when the shaft is in its lower position the gear ring 46 engages teeth 48 on a rotating collar 50, further teeth 54 on the collar driving the platform teeth 16 through gearing 55, 56. When the shaft 12 is raised as shown in Figs. 1, 4 the gears 46, 48 disengage and the gear ring 45 engages a pinion secured to thelower end of a vertical drive shaft (Fig. 6, not shown) of the selected winch 18. The winches are constructed as disclosed in Specification 4534/63 and automatic alignment between the gear teeth on the shaft 12 and the co-operating gear teeth is assured by the arrangement disclosed in Specification 4532/63.
GB4533/63A 1963-02-04 1963-02-04 Improvements relating to fuelling machines for nuclear reactors Expired GB1083460A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB4533/63A GB1083460A (en) 1963-02-04 1963-02-04 Improvements relating to fuelling machines for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB4533/63A GB1083460A (en) 1963-02-04 1963-02-04 Improvements relating to fuelling machines for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1083460A true GB1083460A (en) 1967-09-13

Family

ID=9778980

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4533/63A Expired GB1083460A (en) 1963-02-04 1963-02-04 Improvements relating to fuelling machines for nuclear reactors

Country Status (1)

Country Link
GB (1) GB1083460A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0048671A1 (en) * 1980-09-22 1982-03-31 Novatome Energy production installation comprising several fast neutron nuclear reactors and a fuel element exchange system
FR2555561A1 (en) * 1983-11-24 1985-05-31 Karlsruhe Wiederaufarbeit GRAVITY ACTUATED GRAPPLE FOR ENTERING SHELLS WITH RADIO-ACTIVE CONTENT

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0048671A1 (en) * 1980-09-22 1982-03-31 Novatome Energy production installation comprising several fast neutron nuclear reactors and a fuel element exchange system
FR2555561A1 (en) * 1983-11-24 1985-05-31 Karlsruhe Wiederaufarbeit GRAVITY ACTUATED GRAPPLE FOR ENTERING SHELLS WITH RADIO-ACTIVE CONTENT

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