ES352674A1 - Nuclear reactor fuel charge-discharge installation - Google Patents

Nuclear reactor fuel charge-discharge installation

Info

Publication number
ES352674A1
ES352674A1 ES352674A ES352674A ES352674A1 ES 352674 A1 ES352674 A1 ES 352674A1 ES 352674 A ES352674 A ES 352674A ES 352674 A ES352674 A ES 352674A ES 352674 A1 ES352674 A1 ES 352674A1
Authority
ES
Spain
Prior art keywords
tube
thimble
lock
pit
winch
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
ES352674A
Other languages
Spanish (es)
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of ES352674A1 publication Critical patent/ES352674A1/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
    • 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
    • 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
    • G21C19/18Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

A heavy water moderated gas-cooled reactor core 12 is refuelled through channels 13 extending through a slab 19 into a space 18 provided in the pressure vessel 10. The refuelling is performed by a handling facility A described in Specification 1,219,795 which may place a number of spent fuel elements end-to-end in a thimble (Fig. 4, not shown) secured by a lock to the upper end of a pit 20. There are a number of pits 20 but only one is shown, and in alignment with each pit is a passage 30 extending through the roof of the pressure vessel to a metal dome 32 enclosing a winch (Fig. 2, not shown). An extension 48 of the pit leads to a lock 54 controlled by valves 60, 61, the thimble being unlocked and then lowered by a grab controlled by the winch into the lock where it is again locked. Whilst the thimble is in the pit 20, extension 48 and lock 54 it is cooled by the reactor coolant gas. For emergency use, the lock is surrounded by a box 58 through which water may be circulated. The thimble, after unlocking and opening of valve 61 is lowered by a tappet 78 into a magazine tube 72, the magazine then being rotated so that tube 72 lies beneath guide tube 71. A grab operated by a winch 82 lifts the fuel elements one-by-one from the thimble and places each element in a tube 84 leading to a storage pool 86. New fuel elements on a carriage 88 are introduced by lowering them by a gantry 90 through a tube 92 into a magazine tube.
ES352674A 1967-04-21 1968-04-11 Nuclear reactor fuel charge-discharge installation Expired ES352674A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR103795A FR1527225A (en) 1967-04-21 1967-04-21 Nuclear reactor fuel loading and unloading facility

Publications (1)

Publication Number Publication Date
ES352674A1 true ES352674A1 (en) 1970-10-16

Family

ID=8629448

Family Applications (1)

Application Number Title Priority Date Filing Date
ES352674A Expired ES352674A1 (en) 1967-04-21 1968-04-11 Nuclear reactor fuel charge-discharge installation

Country Status (6)

Country Link
BE (1) BE713093A (en)
CH (1) CH489094A (en)
ES (1) ES352674A1 (en)
FR (1) FR1527225A (en)
GB (1) GB1221020A (en)
LU (1) LU55856A1 (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2154363B2 (en) * 1971-11-02 1979-01-11 Kraftwerk Union Ag, 4330 Muelheim Straight through filter
FR2431752A1 (en) * 1978-07-20 1980-02-15 Commissariat Energie Atomique Enclosure confining water-cooled nuclear reactor - has partitions radiating from central column forming compartments serving as fuel assemblage storage pond and borated water reservoir
FR2445589A1 (en) * 1978-12-29 1980-07-25 Commissariat Energie Atomique Transfer container for radioactive nuclear fuel elements - comprises finned double-walled cylindrical vessel with cooling water circulation, ensuring cooling of element in all circumstances
FR2486297A1 (en) * 1980-07-01 1982-01-08 Novatome DEVICE FOR LOADING AND UNLOADING COMBUSTIBLE ASSEMBLIES FOR FAST NEUTRON NUCLEAR REACTOR
RU2300817C2 (en) * 2005-06-30 2007-06-10 ФГУП Опытное конструкторское бюро "ГИДРОПРЕСС" Nuclear steam-generating plant
RU2393562C1 (en) * 2009-02-16 2010-06-27 Федеральное государственное унитарное предприятие "Всероссийский Электротехнический институт им. В.И. Ленина" (ФГУП ВЭИ) Undeground nuclear heat power plant of vertical shaft design
GB2588842A (en) * 2020-07-23 2021-05-12 Rolls Royce Plc Nuclear refuelling device

Also Published As

Publication number Publication date
BE713093A (en) 1968-08-16
CH489094A (en) 1970-04-15
FR1527225A (en) 1968-05-31
GB1221020A (en) 1971-02-03
LU55856A1 (en) 1968-07-03

Similar Documents

Publication Publication Date Title
US2992174A (en) Breeder-converter reactor
US4056435A (en) Loading and unloading of a nuclear reactor core
US3354041A (en) Nuclear reactor refuelling device
CN109378096B (en) Reactor core refueling method for deep pool type low-temperature heat supply reactor
ES352674A1 (en) Nuclear reactor fuel charge-discharge installation
JPH0335195A (en) Method and structure of shielding radiation from structure in storing condition
GB1366621A (en) Device for permitting or facilitating the handling of the elements which form a nuclear reactor core
US3533911A (en) Nuclear reactor systems
US4663114A (en) Apparatus for handling nuclear fuel assemblies and assembly adapted to such an apparatus
GB849277A (en) Improvements in nuclear reactors
GB1148154A (en) Refuelling apparatus for a nuclear reactor
US3297541A (en) Nuclear reactor core structure
US3072554A (en) Radiation protection means during the exchange of fuel elements
GB943118A (en) Nuclear reactors
GB932794A (en) Improvements in or relating to remotely controlled plant for transferring nuclear fuel elements to a reactor
US3513070A (en) Nuclear power plant containing at least one light water nuclear reactor and one heavy water nuclear reactor
GB1219795A (en) Nuclear reactor refuelling installation
US3219540A (en) Reflectors for nuclear reactors having removable solid moderator elements
US3175854A (en) Nuclear reactors
GB1089341A (en) Nuclear reactor fuelling arrangements
US3190806A (en) Continuously refueled nuclear reactors
GB866541A (en) Improvements in or relating to nuclear reactor fuel element discharging arrangements
US3276963A (en) Flux trap research nuclear reactor
GB1064382A (en) Device for regulating the power of a nuclear reactor
US3180800A (en) Neutronic reactor including means for unloading and hermetically enclosing spent fuel elements