GB1196915A – Nuclear Reactors
– Google Patents
GB1196915A – Nuclear Reactors
– Google Patents
Nuclear Reactors
Info
Publication number
GB1196915A
GB1196915A
GB3453/67A
GB345367A
GB1196915A
GB 1196915 A
GB1196915 A
GB 1196915A
GB 3453/67 A
GB3453/67 A
GB 3453/67A
GB 345367 A
GB345367 A
GB 345367A
GB 1196915 A
GB1196915 A
GB 1196915A
Authority
GB
United Kingdom
Prior art keywords
membrane
pressure vessel
core
fuel
chamber
Prior art date
1966-09-09
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
GB3453/67A
Inventor
Michael Kevin Shaw
Peter Orszak
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.)
English Electric Co Ltd
Original Assignee
English Electric Co 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.)
1966-09-09
Filing date
1966-09-09
Publication date
1970-07-01
1966-09-09
Application filed by English Electric Co Ltd
filed
Critical
English Electric Co Ltd
1966-09-09
Priority to GB3453/67A
priority
Critical
patent/GB1196915A/en
1967-01-24
Priority to GB3363/68A
priority
patent/GB1198001A/en
1967-08-18
Priority to FR118236A
priority
patent/FR1534412A/en
1967-09-08
Priority to DE19671589745
priority
patent/DE1589745A1/en
1968-01-23
Priority to FR137021A
priority
patent/FR1564562A/fr
1970-07-01
Publication of GB1196915A
publication
Critical
patent/GB1196915A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C1/00—Reactor types
G21C1/04—Thermal reactors ; Epithermal reactors
G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C1/00—Reactor types
G21C1/04—Thermal reactors ; Epithermal reactors
G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C13/00—Pressure vessels; Containment vessels; Containment in general
G21C13/02—Details
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C13/00—Pressure vessels; Containment vessels; Containment in general
G21C13/02—Details
G21C13/04—Arrangements for expansion and contraction
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
1,196,915. Reactors. ENGLISH ELECTRIC CO. Ltd. 6 Sept., 1967 [9 Sept., 1966; 24 Jan., 1967], Nos. 40491/66 and 3453/67. Heading G6C. A nuclear reactor comprises a pressure vessel having an internal wall surface enclosing two spaces separated from each other by a membrane having a peripheral edge disposed substantially in a plane, the membrane being sealed at its edge to the internal wall surface of the pressure vessel by a peripheral resilient seal which allows movement in the plane of the edge relative to the internal wall surface. In one example, the membrane separates an inlet space for relatively cool coolant, which space includes the reactor core, from a » hot box » or coolant outlet chamber in a split-flow reactor. The junction between the membrane and the pressure vessel wall is liable to substantial relative movement. As shown in Fig. 1, a concrete pressure vessel 10 is divided by a membrane 11 into a coolant outlet chamber 12 and a larger core chamber 13 in which there is a reactor core 14 (supported on means not shown) having longitudinal fuel channels 15. Each fuel channel 15 includes a fuel stringer 43 comprising a stack of fuel elements, each of which is in the form of a graphite sleeve containing nuclear fuel pins, and connected with a plug (not shown) in a standpipe 17 penetrating the roof 18 of the pressure vessel 10, by means passing through an open-ended connecting tube assembly 29 which extends from the corresponding standpipe 17 down through the hot box 12 to a joint with the top end of an extension tube 16 fixed to and passing through the membrane 11. Coolant gas enters the core chamber 13 through an inlet 21 and some of the gas enters the lower ends of the fuel stringers 43, the remainder by-passing the core 14 and entering the top ends of the fuel channels 15, passing down the channels and into the fuel stringers 43 through openings 20. All the gas passes up inside the fuel stringers 43, extension tubes 16 and tube assemblies 29, through openings 19 into the hot box 12 and then through outlets 22. The pressure vessel wall is maintained at a relatively low temperature by suitable thermal insulation and cooling arrangements, and since the membrane 11 is at a much higher temperature during operation, it is liable to undergo substantial expansion and contraction. Further movement may arise due to pressure differences between the gas in the hot box 12 and that in the core chamber 13, and due to external forces such as may be imposed by prestressing means in the concrete. The membrane 11 is therefore joined by a resilient peripheral seal 32 to a frusto-conical skirt 33 fixed to the steel liner of the pressure vessel 10. Suitable thermal insulation is provided over the whole internal surface of the hot box 12, and over the steel liner and the underside of the skirt 33 in the core chamber 13. The seal could be between the pressure vessel wall and the skirt, instead of between the skirt and the membrane. The skirt is preferably frusto-conical, though it may also be frusto-spherical or cylindrical, and may itself be resilient. The invention may relate to dividing walls other than between a coolant inlet space and a coolant outlet chamber, e.g. the latter may have such a dividing wall on the side remote from the core, separating the interior of the chamber from a space through which coolant fluid is passed for cooling the adjacent part of the pressure vessel. Yet again, the dividing wall may form part of the core support structure below the core, separating a coolant inlet chamber above the membrane from a coolant outlet space below it, or vice versa. 1,196,936. Multipliers. GENERAL ELECTRIC CO. 16 Jan., 1967 [10 Jan., 19671, No. 37801/67. Heading G4G. [Also in Divisions H2 and H3] A D.C. to A.C. converter comprises at least one shunt switch 18 arranged to clamp a circuit between D.C. input and A.C. output E2 to a predetermined potential, said switch 18 being controlled by pulses the duration of which is modulated at the required output frequency. Preferably a pair of shunt switches 18, 19, operating alternately, are employed so as to minimise the D.C. level at the output. Switches 18, 19 may each consist of a transistor connected between the junctions of resistors R4, R5; R7, R8 to earth. A multiplying function may be provided by modulating the 400 Hz. signal fed to the pulse width modulator 12.
GB3453/67A
1966-09-09
1966-09-09
Nuclear Reactors
Expired
GB1196915A
(en)
Priority Applications (5)
Application Number
Priority Date
Filing Date
Title
GB3453/67A
GB1196915A
(en)
1966-09-09
1966-09-09
Nuclear Reactors
GB3363/68A
GB1198001A
(en)
1966-09-09
1967-01-24
Nuclear Reactors
FR118236A
FR1534412A
(en)
1966-09-09
1967-08-18
Nuclear reactor
DE19671589745
DE1589745A1
(en)
1966-09-09
1967-09-08
Nuclear reactor
FR137021A
FR1564562A
(en)
1966-09-09
1968-01-23
Applications Claiming Priority (2)
Application Number
Priority Date
Filing Date
Title
GB3453/67A
GB1196915A
(en)
1966-09-09
1966-09-09
Nuclear Reactors
GB4049166
1966-09-09
Publications (1)
Publication Number
Publication Date
GB1196915A
true
GB1196915A
(en)
1970-07-01
Family
ID=26238310
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB3453/67A
Expired
GB1196915A
(en)
1966-09-09
1966-09-09
Nuclear Reactors
Country Status (3)
Country
Link
DE
(1)
DE1589745A1
(en)
FR
(1)
FR1564562A
(en)
GB
(1)
GB1196915A
(en)
Cited By (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
DE2922368A1
(en)
*
1979-06-01
1980-12-04
Hochtemperatur Reaktorbau Gmbh
Peripheral seal for gas cooled reactors – with sealing strip urged by spring-loaded cylinders into conical gap
1966
1966-09-09
GB
GB3453/67A
patent/GB1196915A/en
not_active
Expired
1967
1967-09-08
DE
DE19671589745
patent/DE1589745A1/en
active
Pending
1968
1968-01-23
FR
FR137021A
patent/FR1564562A/fr
not_active
Expired
Cited By (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
DE2922368A1
(en)
*
1979-06-01
1980-12-04
Hochtemperatur Reaktorbau Gmbh
Peripheral seal for gas cooled reactors – with sealing strip urged by spring-loaded cylinders into conical gap
Also Published As
Publication number
Publication date
DE1589745A1
(en)
1970-05-21
FR1564562A
(en)
1969-04-25
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Legal Events
Date
Code
Title
Description
1971-07-07
CSNS
Application of which complete specification have been accepted and published, but patent is not sealed
