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GB1064820A - Handling machine for nuclear reactors - Google Patents

Handling machine for nuclear reactors

Info

Publication number
GB1064820A
GB1064820A GB50025/63A GB5002563A GB1064820A GB 1064820 A GB1064820 A GB 1064820A GB 50025/63 A GB50025/63 A GB 50025/63A GB 5002563 A GB5002563 A GB 5002563A GB 1064820 A GB1064820 A GB 1064820A
Authority
GB
United Kingdom
Prior art keywords
compartment
grab
main
magazine
fuel element
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
GB50025/63A
Inventor
Jean Hainzelin
Robert Clausse
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.)
Electricite de France SA
Original Assignee
Electricite de France SA
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 Electricite de France SA filed Critical Electricite de France SA
Publication of GB1064820A publication Critical patent/GB1064820A/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
    • G21C19/16Articulated or telescopic chutes or tubes for connection to channels in the reactor core
    • 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
    • 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
    • G21C19/32Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • 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)

Abstract

1,064,820. Fuelling and servicing reactors. ELECTRICITE DE FRANCE. Dec. 18, 1963 [Dec. 20, 1962], No. 50025/63. Heading G6C. A fuelling and servicing machine is movable by a transporter (not shown) over a reactor so that a main conduit 1 may be connected by a bellows seal 3 to a selected standpipe 2 upon the lowering of a shielding section 11a by jacks 34. Similarly, by lowering the section 11a an auxiliary conduit 18 may be connected at its lower end 15 to a tube (not shown) leading to a store for spent or new fuel elements. The lower part of the machine enclosed by shielding sections 11a ... 11e is disconnectible by bolts from the main part enclosed by sections 59a ... 59j so that should the machine fail whilst coupled to a standpipe the main part may be removed after closing a valve 35 in the conduit 1. A main pressure vessel 50a, 50b, 50c pressurized with gas at the reactor pressure has a bottom plate 51 with openings 52, 53 aligned with the conduits 18, 1. The top plate 54 of the pressure vessel has openings 55, 57 giving access to removable auxiliary pressure vessels 56, 58, respectively, this access being controlled by valves 71, 72. A main magazine 61 within the main pressure vessel is suspended by a bearing 81 from the top plate 54 and guided at the lower end in the plate 51 by a bearing 83. The magazine 61 has compartments A ... F which may be aligned with the conduit 1 and housing these components; compartment A- spent plug stringer; compartment B-control rod guide tube; compartment C-emergeney servicing canister; compartment D-charge shoot or one new control rod and one spent control rod; compartment E - new plug stringer; compartment F-fuel element guide tube, when the latter tube is lowered compartment F then serves for discharging the fuel element channels of the reactor. A magazine 62 surrounding the lower part of magazine 61 is supported by a bearing 96 on the plate 51 and has twenty-four chambers 63 which may be aligned with the conduit 18 and each receiving a removable canister for containing fuel elements. A fuel element grab 67 is movable about an eccentric vertical axis 100 by a unit 65 so that it may be aligned either with the compartment F or with a chamber 63. The pressure vessel 56 contains a main hoist 129 controlling a main grab 132, this grab lifting the charge shoot, plug stringer, control rod guide tube and seal plugs of fuel element storage facilities. An auxiliary grab 133, also in the vessel 56 and controlled by an auxiliary hoist 134, is movable transversely out of the way of the main grab 132 and serves to lift the control rods and associated gear and fuel element guide tube. The pressure vessel 58 contains a hoist 157 for controlling a grab 70 for lifting the fuel element canister. In a fuelling operation, after coupling the machine to a standpipe 2 the grabs 132, 133 are used to remove certain components from the standpipe and place them in empty compartments of the magazine 61 and to lower various components from other compartments of the magazine 61 in preparation for the transfer of the fuel elements. The fuel element grab 67 now lifts the spent fuel elements through the magazine compartment F and is moved transversely by the unit 65 to deposit the fuel elements in the canisters in chambers 63. In order to remove the spent fuel elements from the machine the latter is moved so that the conduit 18 may be coupled to a spent fuel store and the grab 70 in the vessel 58 is lowered through a fixed guide tube 64 to lower the canisters from the chambers 63 through the conduit 18. The Specification also describes the procedure for the removal of a burst fuel element and the renewal of a control rod. The machine is cooled by gas circulated under pressure by a turbo-blower. In the event of a fault in a fuel element channel of the reactor preventing discharge of that channel the auxiliary pressure vessel 56 is removed and replaced by an emergency servicing flask containing a T.V. camera and special tools. Further, the auxiliary pressure vessel 58 may be replaced by a sealed flask containing a grab in the event of a fault in the machine.
GB50025/63A 1962-12-20 1963-12-18 Handling machine for nuclear reactors Expired GB1064820A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR919347A FR1354866A (en) 1962-12-20 1962-12-20 Improvements to handling machines for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1064820A true GB1064820A (en) 1967-04-12

Family

ID=8793330

Family Applications (1)

Application Number Title Priority Date Filing Date
GB50025/63A Expired GB1064820A (en) 1962-12-20 1963-12-18 Handling machine for nuclear reactors

Country Status (4)

Country Link
BE (1) BE641544A (en)
FR (1) FR1354866A (en)
GB (1) GB1064820A (en)
LU (1) LU44988A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109979626A (en) * 2017-12-27 2019-07-05 核动力运行研究所 A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021248387A1 (en) * 2020-06-10 2021-12-16 中广核研究院有限公司 Refueling transfer device, and refueling method
CN113724905B (en) * 2021-08-24 2024-02-20 中国原子能科学研究院 Grabbing equipment
CN115064291B (en) * 2022-03-18 2024-02-20 中国原子能科学研究院 Positioning and centering device and method for closed type refueling system of reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109979626A (en) * 2017-12-27 2019-07-05 核动力运行研究所 A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method
CN109979626B (en) * 2017-12-27 2024-04-09 核动力运行研究所 Swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method

Also Published As

Publication number Publication date
LU44988A1 (en) 1964-02-11
FR1354866A (en) 1964-03-13
BE641544A (en) 1964-04-16

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