GB1382797A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB1382797A
GB1382797A GB5140571A GB5140571A GB1382797A GB 1382797 A GB1382797 A GB 1382797A GB 5140571 A GB5140571 A GB 5140571A GB 5140571 A GB5140571 A GB 5140571A GB 1382797 A GB1382797 A GB 1382797A
Authority
GB
United Kingdom
Prior art keywords
sub
transfer
gripper
assembly
transfer member
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
GB5140571A
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.)
British Nuclear Design of Construction Ltd
Original Assignee
British Nuclear Design of Construction 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 British Nuclear Design of Construction Ltd filed Critical British Nuclear Design of Construction Ltd
Priority to GB5140571A priority Critical patent/GB1382797A/en
Priority to FR7238965A priority patent/FR2158491B1/fr
Publication of GB1382797A publication Critical patent/GB1382797A/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
    • G21C19/20Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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)
  • Load-Engaging Elements For Cranes (AREA)

Abstract

1382797 Refuelling reactors BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd 3 Nov 1972 [4 Nov 1971] 51405/71 Heading G6C A nuclear reactor comprises a transfer machine 20 which acts to transfer fuel-elements or other components from core-discharging apparatus to a storage facility and vice versa. The machine 20 is disposed laterally of the core 12 and has a transfer member 22 movable on a pantograph mechanism 21 between or transfer position in which it transfers a component such as a full sub-assembly 32 to or from a respective gripper 18 of a charging machine 16 or 17 (which has been appropriately positioned by rotation of closure plugs 14, 15) and a datum position beneath a gripper 23 for transferring the sub-assembly 32 from or to a careusel 24 to which access may be had, via tube 29, from the exterior of the reactor. The transfer member 22 is constructed to receive a bottom spigot 33 which normally locates the sub-assembly 32 in the core 12, and provides a pad 42 to support the sub-assembly 32 at a slight inclination. The transfer member may be arranged to support two sub-assemblies 32 simultaneously (Fig. 4, not shown) to speed up the refuelling operation by reducing the member of transfer movements. The charging machines 16, 17 may be rotatable relative to the closure plug 15 and may include means to hold down core components adjacent the one being removed. In modifications (Figs. 6 and 7, not shown), the gripper 18 and the transfer member 22 are constructed to provide interference members which coact to prevent, respectively, release of a sub-assembly 32, whose spigot 33 is damaged or missing, from the gripper 18 to the transfer member 22, and movement of the transfer member 22 away from the transfer position until the gripper 18 is fully clear of a fuel subassembly. In the core 12, the sub-assemblies 32 may be disposed at a slight angle to the vertical and supported by leaning posts so as to reduce their vibration due to flow of the sodium coolant.
GB5140571A 1971-11-04 1971-11-04 Nuclear reactors Expired GB1382797A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB5140571A GB1382797A (en) 1971-11-04 1971-11-04 Nuclear reactors
FR7238965A FR2158491B1 (en) 1971-11-04 1972-11-03

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB5140571A GB1382797A (en) 1971-11-04 1971-11-04 Nuclear reactors

Publications (1)

Publication Number Publication Date
GB1382797A true GB1382797A (en) 1975-02-05

Family

ID=10459883

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5140571A Expired GB1382797A (en) 1971-11-04 1971-11-04 Nuclear reactors

Country Status (2)

Country Link
FR (1) FR2158491B1 (en)
GB (1) GB1382797A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4961899A (en) * 1984-08-23 1990-10-09 Westinghouse Electric Corp. Multiple-cable connecting device for a nuclear reactor
WO2011067230A1 (en) 2009-12-02 2011-06-09 Commissariat A L'energie Atomique Et Aux Energies Alternatives Device and method assisting the loading and unloading of the core of a nuclear reactor and sodium-cooled nuclear reactor including such a device

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4069098A (en) * 1976-02-23 1978-01-17 Westinghouse Electric Corporation Ex-vessel nuclear fuel transfer system
US5019327A (en) * 1990-01-25 1991-05-28 General Electric Company Fuel assembly transfer basket for pool type nuclear reactor vessels
FR3019931B1 (en) * 2014-04-11 2016-05-13 Commissariat Energie Atomique UNIT FOR LOADING / UNLOADING COMBUSTIBLE ASSEMBLIES OF A METALLIQUID COOLED REACTOR, SUCH AS A RNR-NA OR SFR REACTOR, INCORPORATING A DEVICE FOR MEASURING THE RESIDUAL POWER

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE573083A (en) * 1957-11-18

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4961899A (en) * 1984-08-23 1990-10-09 Westinghouse Electric Corp. Multiple-cable connecting device for a nuclear reactor
WO2011067230A1 (en) 2009-12-02 2011-06-09 Commissariat A L'energie Atomique Et Aux Energies Alternatives Device and method assisting the loading and unloading of the core of a nuclear reactor and sodium-cooled nuclear reactor including such a device

Also Published As

Publication number Publication date
FR2158491B1 (en) 1978-03-03
FR2158491A1 (en) 1973-06-15

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee