GB1306655A

GB1306655A – Nuclear reactor of the type comprising a core cover
– Google Patents

GB1306655A – Nuclear reactor of the type comprising a core cover
– Google Patents
Nuclear reactor of the type comprising a core cover

Info

Publication number
GB1306655A

GB1306655A
GB4661871A
GB4661871A
GB1306655A
GB 1306655 A
GB1306655 A
GB 1306655A
GB 4661871 A
GB4661871 A
GB 4661871A
GB 4661871 A
GB4661871 A
GB 4661871A
GB 1306655 A
GB1306655 A
GB 1306655A
Authority
GB
United Kingdom
Prior art keywords
core
plug
reactor
shield
handling
Prior art date
1970-10-15
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
GB4661871A
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.)
1970-10-15
Filing date
1971-10-07
Publication date
1973-02-14

1971-10-07
Application filed by Commissariat a lEnergie Atomique CEA
filed
Critical
Commissariat a lEnergie Atomique CEA

1973-02-14
Publication of GB1306655A
publication
Critical
patent/GB1306655A/en

Status
Expired
legal-status
Critical
Current

Links

Espacenet

Global Dossier

Discuss

Classifications

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C13/00—Pressure vessels; Containment vessels; Containment in general

G21C13/02—Details

G21C13/06—Sealing-plugs

G21C13/073—Closures for reactor-vessels, e.g. rotatable

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

G21C19/16—Articulated or telescopic chutes or tubes for connection to channels in the reactor core

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

Abstract

1306655 Fuelling reactors COMMISSARIAT A L’ENERGIE ATOMIQUE 7 Oct 1971 [15 Oct 1970] 46618/71 Heading G6C A reactor has two rotatable shield plugs 6 and 8, the inner plug 8 which supports a core cover 10 by means of an axial extension 9 being mounted eccentrically within the outer plug 6 which is disposed in coaxial relation to the reactor core 1. The inner plug 8 has a smaller diameter than the core 1 and the cover 10 which it carries forms above the core a lateral projection with respect to the plug 8, the rotation of this plug about its own axis being intended to expose part of the reactor core as so to permit handling of fuel assemblies within the core by means of an articulated handling arm 20 which is carried by the outer plug 6. The core cover 10 serves as a collector for all the instruments and devices which are intended for measurements or tests to be carried out on the fuel assemblies of the core 1. Control rod guide tubes 12 pass through the shield plugs 6, 8 and are movable downwardly to enter passageways 11 in the core cover 10 when in alignment therewith as in the case of the right hand guide tube 12 in the Figure. The handling arm 20 has articulated link rods 21 for adjusting the position of a grappling system 22, and the operation of this arm 20 in conjunction with the rotation of the shield plug 6 permits the removal of a fuel assembly from any one of the core channels 18 and its transfer to a fuel-handling flask 24 located outside the core blanket 14. The flask 24 is supported by a device 26 movable within a discharge duct 28 secured within the top wall 4 of the reactor shield. The core cover 10 is shown in full outline in its position exposing part of the core 1 and in broken outline in its position for normal reactor operation. The core 1 and blanket 14 are surrounded within the reactor vessel 2 by a neutron shield comprising a lateral wall 30 having a top shield extension constituted by a plate 32, suspended from the outer plug 6 and penetrated by an opening 34 through which the inner plug extension 9 passes, and by a disc 36 contained within the extension 9. The plate 32 is penetrated by a radial passage 38 for the insertion of the handling arm 20 which permits lateral movement of the grappling system 22 towards the core channels 18 or the handling flask 24.

GB4661871A
1970-10-15
1971-10-07
Nuclear reactor of the type comprising a core cover

Expired

GB1306655A
(en)

Applications Claiming Priority (1)

Application Number
Priority Date
Filing Date
Title

FR7037310A

FR2116204B1
(en)

1970-10-15
1970-10-15

Publications (1)

Publication Number
Publication Date

GB1306655A
true

GB1306655A
(en)

1973-02-14

Family
ID=9062813
Family Applications (1)

Application Number
Title
Priority Date
Filing Date

GB4661871A
Expired

GB1306655A
(en)

1970-10-15
1971-10-07
Nuclear reactor of the type comprising a core cover

Country Status (5)

Country
Link

US
(1)

US3773616A
(en)

DE
(1)

DE2151242A1
(en)

FR
(1)

FR2116204B1
(en)

GB
(1)

GB1306655A
(en)

IT
(1)

IT943451B
(en)

Families Citing this family (14)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

FR2188251B1
(en)

*

1972-06-08
1976-01-16
Commissariat A En Atomique Fr

US4142935A
(en)

*

1975-04-09
1979-03-06
Westinghouse Electric Corp.
Nuclear reactor

US4053356A
(en)

*

1975-08-08
1977-10-11
Westinghouse Electric Corporation
Guide device

US4062723A
(en)

*

1975-09-29
1977-12-13
Combustion Engineering, Inc.
Core access system for nuclear reactor

US4064000A
(en)

*

1975-09-29
1977-12-20
Combustion Engineering, Inc.
Nuclear reactor core servicing apparatus

US4116765A
(en)

*

1976-04-27
1978-09-26
Commissariat A L’energie Atomique
Liquid metal cooled nuclear reactor

US4096031A
(en)

*

1976-07-22
1978-06-20
Westinghouse Electric Corp.
Nuclear reactor refueling system

FR2368121A1
(en)

*

1976-10-15
1978-05-12
Commissariat Energie Atomique

DOUBLE ARM HANDLING DEVICE FOR NUCLEAR REACTOR

FR2488719B1
(en)

*

1980-08-14
1985-10-04
Commissariat Energie Atomique

INSTALLATION AND METHOD FOR HANDLING FAST NEUTRAL NUCLEAR REACTOR ASSEMBLIES

JPS6040995A
(en)

*

1983-08-16
1985-03-04
動力炉・核燃料開発事業団
Liquid metal cooling fast breeder reactor

US4645640A
(en)

*

1984-02-09
1987-02-24
Westinghouse Electric Corp.
Refueling system with small diameter rotatable plugs

FR2793719B1
(en)

*

1999-05-18
2001-06-29
Cogema

ARTICULATED ARM TO DESCEND UNDER A SLAB

US9761332B2
(en)

*

2014-06-09
2017-09-12
Bwxt Mpower, Inc.
Nuclear reactor neutron shielding

RU2638032C1
(en)

*

2017-03-10
2017-12-11
Общество с ограниченной ответственностью “Пролог”
Device for conducting load and carry operations in reactor room of nuclear power station

1970

1970-10-15
FR
FR7037310A
patent/FR2116204B1/fr
not_active
Expired

1971

1971-10-07
GB
GB4661871A
patent/GB1306655A/en
not_active
Expired

1971-10-13
US
US00188813A
patent/US3773616A/en
not_active
Expired – Lifetime

1971-10-14
DE
DE19712151242
patent/DE2151242A1/en
active
Pending

1971-10-14
IT
IT70376/71A
patent/IT943451B/en
active

Also Published As

Publication number
Publication date

US3773616A
(en)

1973-11-20

IT943451B
(en)

1973-04-02

FR2116204A1
(en)

1972-07-13

DE2151242A1
(en)

1972-06-22

FR2116204B1
(en)

1974-04-26

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Device comprising a chamber and suitable for manipulating components of nuclear reactors

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(en)

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Apparatus for measuring the local neutron density distribution in the interior of a nuclear reactor

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(en)

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Legal Events

Date
Code
Title
Description

1973-06-27
PS
Patent sealed [section 19, patents act 1949]

1976-02-18
435
Patent endorsed ‘licences of right’ on the date specified (sect. 35/1949)

1979-05-16
PCNP
Patent ceased through non-payment of renewal fee

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