GB917606A - Improvements in or relating to pressurised fluid-cooled nuclear reactors - Google Patents

Improvements in or relating to pressurised fluid-cooled nuclear reactors

Info

Publication number
GB917606A
GB917606A GB38328/60A GB3832860A GB917606A GB 917606 A GB917606 A GB 917606A GB 38328/60 A GB38328/60 A GB 38328/60A GB 3832860 A GB3832860 A GB 3832860A GB 917606 A GB917606 A GB 917606A
Authority
GB
United Kingdom
Prior art keywords
coolant
vessel
reactor
standpipes
gas
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
GB38328/60A
Inventor
John Henry Wilson
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.)
General Electric Co PLC
Simon Carves Ltd
Carves Simon Ltd
Original Assignee
General Electric Co PLC
Simon Carves Ltd
Carves Simon 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 General Electric Co PLC, Simon Carves Ltd, Carves Simon Ltd filed Critical General Electric Co PLC
Priority to GB38328/60A priority Critical patent/GB917606A/en
Priority to FR878367A priority patent/FR1306796A/en
Publication of GB917606A publication Critical patent/GB917606A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment 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

Abstract

917,606. Nuclear reactors. SIMON-CARVES Ltd., and GENERAL ELECTRIC CO. Ltd. Nov. 2, 1961 [Nov. 8, 1960], No. 38328/60. Class 39 (4). A pressurized fluid-cooled nuclear reactor in which the reactor core is housed within a concrete pressure vessel whose inner surface is adapted to be cooled by coolant flowing in heat exchange relationship with the surface independently of the main reactor coolant. The reactor comprises a graphite core 1 within a concrete pressure vessel 3. Pressurized coolant gas enters the core through the ducts 4, flows through the vertical fuel elements, and is exhausted by way of ducts 5 to four heat exchangers (not shown). Access to the core is provided by standpipes 7, while further standpipes (not shown) are placed at the side of the reactor to enable samples of gas to be extracted for monitoring purposes. The whole of the inner surface of the vessel 3 is lined with a gasimpervious steel membrane 9, and spaced from this membrane, forming an annulus, is another steel membrane 14 constituting a heat insulator. Heat is removed from the walls of the vessel by three primary circuits each of which is provided with auxiliary circuits. In the first circuit gas enters the vessel through six inlets 17 and passes up the sides of the vessel in the annular space between the membranes 9 and 14. At the crown of the vessel the gas is guided radially inwards and is extracted through twelve nozzles (not shown) disposed between the standpipes 7 in two circular patterns. The main reactor and coolant pressures are equalized by providing small holes 22 in the membrane 14, however interchange of gases is discouraged by placing screens 23 in front of the holes. Gas entering the pipe 24 and leaving the pipe 27 provides a parallel auxiliary coolant circuit for the duct 5. The second primary circuit, which cools the bottom of the vessel and the ducts 4, enters the space between the membranes through the pipe 28, is guided by baffles 29 and leaves through the pipe 30. Again the membrane 14 is provided with holes to equalise the adjacent pressures. Parallel auxiliary circuits cool the ducts 4, inlet pipes 32 and outlet pipes 33 being used for this purpose. The third primary circuit cools the standpipes 7 by allowing the coolant gas to flow in the annulus formed between the standpipe and its sleeve. The standpipes are arranged in groups of eight, the coolant of those in the same group flows in series, while that of different groups flows in parallel and is connected to headers 41 and 42. The pressure of this circuit is less than the reactor coolant so that contamination of the latter is avoided.
GB38328/60A 1960-11-08 1960-11-08 Improvements in or relating to pressurised fluid-cooled nuclear reactors Expired GB917606A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB38328/60A GB917606A (en) 1960-11-08 1960-11-08 Improvements in or relating to pressurised fluid-cooled nuclear reactors
FR878367A FR1306796A (en) 1960-11-08 1961-11-08 Nuclear reactor cooled by pressurized fluid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB38328/60A GB917606A (en) 1960-11-08 1960-11-08 Improvements in or relating to pressurised fluid-cooled nuclear reactors

Publications (1)

Publication Number Publication Date
GB917606A true GB917606A (en) 1963-02-06

Family

ID=10402755

Family Applications (1)

Application Number Title Priority Date Filing Date
GB38328/60A Expired GB917606A (en) 1960-11-08 1960-11-08 Improvements in or relating to pressurised fluid-cooled nuclear reactors

Country Status (1)

Country Link
GB (1) GB917606A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20170372804A1 (en) * 2012-10-11 2017-12-28 Bwxt Technical Services Group, Inc. Fail-Safe Reactivity Compensation Method For A Nuclear Reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20170372804A1 (en) * 2012-10-11 2017-12-28 Bwxt Technical Services Group, Inc. Fail-Safe Reactivity Compensation Method For A Nuclear Reactor
US11043309B2 (en) * 2012-10-11 2021-06-22 Bwxt Technical Services Group, Inc. Fail-safe reactivity compensation method for a nuclear reactor
US20210313081A1 (en) * 2012-10-11 2021-10-07 Bwxt Technical Services Group, Inc. Fail-safe reactivity compensation method for a nuclear reactor

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