GB1182239A - Drive and Coupling Mechanisms for Nuclear Reactor Control Elements. - Google Patents

Drive and Coupling Mechanisms for Nuclear Reactor Control Elements.

Info

Publication number
GB1182239A
GB1182239A GB47682/68A GB4768268A GB1182239A GB 1182239 A GB1182239 A GB 1182239A GB 47682/68 A GB47682/68 A GB 47682/68A GB 4768268 A GB4768268 A GB 4768268A GB 1182239 A GB1182239 A GB 1182239A
Authority
GB
United Kingdom
Prior art keywords
rod
tube
nut
sleeve
fingers
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
GB47682/68A
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.)
Combustion Engineering Inc
Original Assignee
Combustion Engineering Inc
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 Combustion Engineering Inc filed Critical Combustion Engineering Inc
Publication of GB1182239A publication Critical patent/GB1182239A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/10Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/11Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with revolving coupling elements, e.g. socket coupling
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/10Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/105Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/10Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/115Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with latching devices and ball couplings
    • 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
    • G21C7/12Means for moving control elements to desired position
    • 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)
  • Load-Engaging Elements For Cranes (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)

Abstract

1,182,239. Grippers for nuclear fuel elements. COMBUSTION ENG. Inc. 8 Oct., 1968 [10 Oct., 1967], No. 47682/68. Heading B8H. [Also in Division G6] A control element is coupled to a drive mechanism by means of a gripper comprising fingers 64 movable between their locking and unlocking positions by the action of the head 68 of a rod 66. Attached to the rod 66 by means of a pin 70 is a cylindrical member 72 at the lower end of which are camming members 74. The entire gripper operating mechanism reciprocates vertically relative to the fingers 64 and when lowered, the camming members 74 (as shown in Fig. 4) release the fingers 64 and the head 68 forces the fingers apart to release the lifting attachment 75 on the control element. The entire gripper operating mechanism is attached by means of a rotatable joint (not shown) to a rod 76 which extends vertically through a tube 60 screw-threaded at its lower portion 63 to the upper end of the fingers 64 and screwthreaded at its upper portion 61 to a threaded portion 78 on the rod 76. The tube 60 in turn extends vertically through a hollow rack 26 forming part of a rack and pinion drive. An elongated nut-like member 62 is screwthreaded on to the upper portion 61 and the tube 60 is suspended by means of this nut 62 from the head 42 of the rack 26. Since vibration or operation of the drive mechanism could cause the nut 62 to rotate relative to the tube 60, locking means are provided comprising a sleeve 80 extending upwardly from the nut 62 and surrounding the upper portion 61. A lock operator 82 is mounted around the sleeve 80 with pins 84 extending inwardly into slots 86 in the sleeve. A spring 87 between the nut 62 and the operator 82 forces the latter upwardly into a position in which a ball detent mechanism locks the sleeve 80 and thus the nut 62 to the tube 60. In order to unlock and rotate the nut 62 a tool is employed first to depress the operator 82 against the force of the spring 87 and release the detent mechanism and then to rotate the operator 82. The pins 84 cause the nut 62 to rotate, thereby lowering the tube 60 within the rack 26. The control element is uncoupled by lowering the rack 26 as far as possible in which position the control element is located just above the reactor core base and then a first tool is inserted to operate the nut locking mechanism as described above. The tube 60 is then lowered within the rack 26 and the control element thus lowered on to the core base. The tool is then removed and a second tool inserted to operate the grippers. This tool fits over pin 97 at the upper end of the rod 76 and rotates the rod so as to screw it down within the tube 60, causing the gripper operating mechanism to be lowered with respect to the fingers 64 whereby the fingers are opened and the control element released. The rack 26 is then driven to its upper limit of travel. After this procedure has been followed for each of the control element drive assemblies, the head may be removed from the reactor vessel together with the drive assemblies. In an alternative arrangement for raising and lowering the rod 76 within the tube 60 (Figs. 8 and 9, not shown), the tube has a bayonet slot with the hooked end uppermost into which a pin extends. The pin is received in the shorter leg of the bayonet slot when the rod is held within the tube. The pin is attached to the rod by means comprising a sleeve to which the pin is attached extending over the end of the rod, the sleeve being provided with a U-slot with upwardly extending arms, a second pin attached to the rod and extending outwardly so as to be received in one of the legs of the U-slot, a spring biasing the sleeve down on to the end of the rod, and means for lifting the sleeve against the force of the spring and for rotating the sleeve so that the pins take positions in the other legs of the bayonet slot and the U-slot respectively.
GB47682/68A 1967-10-10 1968-10-08 Drive and Coupling Mechanisms for Nuclear Reactor Control Elements. Expired GB1182239A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US67420567A 1967-10-10 1967-10-10

Publications (1)

Publication Number Publication Date
GB1182239A true GB1182239A (en) 1970-02-25

Family

ID=24705727

Family Applications (1)

Application Number Title Priority Date Filing Date
GB47682/68A Expired GB1182239A (en) 1967-10-10 1968-10-08 Drive and Coupling Mechanisms for Nuclear Reactor Control Elements.

Country Status (4)

Country Link
CH (1) CH483084A (en)
DE (1) DE1800789A1 (en)
FR (1) FR1585774A (en)
GB (1) GB1182239A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2496193A1 (en) * 1980-12-16 1982-06-18 Westinghouse Electric Corp MECHANISM FOR LATCHING AND TRANSLATION OF BARS
EP2580762A4 (en) * 2010-06-08 2017-02-08 Westinghouse Electric Company LLC Control rod drive shaft unlatching tool
CN109390063A (en) * 2018-11-06 2019-02-26 中核核电运行管理有限公司 A kind of pressurized-water reactor nuclear power plant reactor core guide post Automatic hook block
US11289222B2 (en) 2018-03-16 2022-03-29 Framatome Inc. Method and device for unlatching control rod drive shafts in pressurized water reactors

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2708786A1 (en) * 1977-03-01 1978-09-07 Haeussler Ernst DEVICE FOR ATTACHING A PRECAST CONCRETE PART TO A HOIST
US4204910A (en) * 1977-08-25 1980-05-27 Batjukov Vladimir I Gripping means for refuelling a nuclear reactor
FR2420826A1 (en) * 1978-03-22 1979-10-19 Commissariat Energie Atomique REMOTELY MOUNTABLE AND REMOVABLE FUEL ASSEMBLY FOR NUCLEAR REACTOR AND CORRESPONDING TOOLS
FR2465911A1 (en) * 1979-09-19 1981-03-27 Framatome Sa DEVICE FOR COUPLING AND REMOTELY DISCHARGING TWO LARGE-LONG ELEMENTS COAXALLY AND END TO END
DE3342471A1 (en) * 1983-11-24 1985-06-05 Wiederaufarbeitungsanlage Karlsruhe Betriebsgesellschaft mbH, 7514 Eggenstein-Leopoldshafen GRAVITY-ACTIVATED GRIPPER FOR DETECTING CHILLERS WITH RADIOACTIVE CONTENT
DE4013228C1 (en) * 1990-04-26 1991-06-27 Man Roland Druckmaschinen Ag, 6050 Offenbach, De
CN114572678B (en) * 2022-03-16 2023-03-21 中国原子能科学研究院 Grabbing mechanism of nuclear power assembly and grabbing device comprising grabbing mechanism

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2496193A1 (en) * 1980-12-16 1982-06-18 Westinghouse Electric Corp MECHANISM FOR LATCHING AND TRANSLATION OF BARS
EP0054788A2 (en) * 1980-12-16 1982-06-30 Westinghouse Electric Corporation Rod drive and latching mechanism
EP0054788A3 (en) * 1980-12-16 1982-09-22 Westinghouse Electric Corporation Rod drive and latching mechanism
EP2580762A4 (en) * 2010-06-08 2017-02-08 Westinghouse Electric Company LLC Control rod drive shaft unlatching tool
US11289222B2 (en) 2018-03-16 2022-03-29 Framatome Inc. Method and device for unlatching control rod drive shafts in pressurized water reactors
CN109390063A (en) * 2018-11-06 2019-02-26 中核核电运行管理有限公司 A kind of pressurized-water reactor nuclear power plant reactor core guide post Automatic hook block
CN109390063B (en) * 2018-11-06 2024-03-19 中核核电运行管理有限公司 Automatic lifting appliance for reactor core guide column of pressurized water reactor nuclear power station

Also Published As

Publication number Publication date
DE1800789A1 (en) 1969-10-16
CH483084A (en) 1969-12-15
FR1585774A (en) 1970-01-30

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Legal Events

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