GB917606A - Improvements in or relating to pressurised fluid-cooled nuclear reactors - Google Patents
Improvements in or relating to pressurised fluid-cooled nuclear reactorsInfo
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- 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
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.
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)
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 |
-
1960
- 1960-11-08 GB GB38328/60A patent/GB917606A/en not_active Expired
Cited By (3)
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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