ES352967A1 - Nuclear reactor refuelling installation - Google Patents

Nuclear reactor refuelling installation

Info

Publication number
ES352967A1
ES352967A1 ES352967A ES352967A ES352967A1 ES 352967 A1 ES352967 A1 ES 352967A1 ES 352967 A ES352967 A ES 352967A ES 352967 A ES352967 A ES 352967A ES 352967 A1 ES352967 A1 ES 352967A1
Authority
ES
Spain
Prior art keywords
grab
winch
lock
carriage
thimble
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
ES352967A
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 ES352967A1 publication Critical patent/ES352967A1/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
    • 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
    • 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
    • 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
    • G21C19/32—Apparatus 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
    • 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)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)

Abstract

A fuel handling arrangement for transferring spent elements from the core 12 of a gas-cooled heavy water moderated reactor to a pond 124 and for introducing new elements comprises a facility A disposed in a space 18 in the pressure vessel 10 above a shielding slab 20. The facility A includes a beam 22 rotatable about the axis of the reactor and supporting a carriage carrying a grab, whereby the grab may be aligned with a selected servicing channel 14 and transfer fuel elements from the core 12 into a thimble (not shown) disposed in a pick-up pit 90. The drive motors for the beam, carriage and grab are contained in a dome 66. An ancillary enclosure 92 contains a lock 100 bounded at one end by valves 96, 98 and at the other end by a valve 104, this lock being in alignment with the pit 90 whereby a grab controlled by a winch 102 may raise the thimble through guide sleeves 95, 94 into the lock, the valve 104 being closed. The thimble is retained in the lock 100 by a latch so that the grab may be disconnected and moved laterally out of alignment with the lock. The valves 96, 98 are closed, the gas pressure in lock 100 is reduced to atmospheric, valve 104 is opened and a grab controlled by a winch 106 is lowered through a guide sleeve 110 to engage the thimble. The winch 106 is supported by a carriage on rails 108 so that the thimble may be lowered through a discharge channel 112 into a receptacle carried by a carriage 118 running on rails 116. Undamaged fuel elements are transferred one-by-one from the carriage 118 by means of a winch 130 through a passage 126 into a duct 133. The duct 133 is carried by an arm movable about a vertical axis whereby the duct may be brought beneath a grab carried by a travelling bridge 132 and the fuel element taken to a selected part of the pond 124. Damaged elements are placed in a flask 140 by means of a winch 135. New fuel elements are introduced into the receptacle carried by carriage 118 by means of a winch 142 situated above a fuel element store 144.
ES352967A 1967-04-21 1968-04-20 Nuclear reactor refuelling installation Expired ES352967A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR103794A FR1527224A (en) 1967-04-21 1967-04-21 Nuclear reactor fuel reloading facility

Publications (1)

Publication Number Publication Date
ES352967A1 true ES352967A1 (en) 1970-10-16

Family

ID=8629447

Family Applications (1)

Application Number Title Priority Date Filing Date
ES352967A Expired ES352967A1 (en) 1967-04-21 1968-04-20 Nuclear reactor refuelling installation

Country Status (6)

Country Link
BE (1) BE712858A (en)
CH (1) CH490725A (en)
ES (1) ES352967A1 (en)
FR (1) FR1527224A (en)
GB (1) GB1219795A (en)
LU (1) LU55874A1 (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1559436A (en) * 1977-05-14 1980-01-16 Timofeev A V Others nuclear reactors
DE2753034C2 (en) * 1977-11-28 1986-10-09 Kraftwerk Union AG, 4330 Mülheim Equipment for the storage of spent nuclear reactor fuel elements and methods for the operation of this equipment
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
FR2475784A1 (en) * 1980-02-08 1981-08-14 Novatome Sa DEVICE FOR TRANSFERRING AND STORING COMBUSTIBLE ASSEMBLIES FOR NUCLEAR REACTORS
US4572710A (en) * 1982-06-14 1986-02-25 General Signal Corporation Method and apparatus for changing filters in nuclear power stations

Also Published As

Publication number Publication date
FR1527224A (en) 1968-05-31
BE712858A (en) 1968-07-31
GB1219795A (en) 1971-01-20
CH490725A (en) 1970-05-15
LU55874A1 (en) 1968-07-09

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