GB1132091A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1132091A GB1132091A GB24794/65A GB2479465A GB1132091A GB 1132091 A GB1132091 A GB 1132091A GB 24794/65 A GB24794/65 A GB 24794/65A GB 2479465 A GB2479465 A GB 2479465A GB 1132091 A GB1132091 A GB 1132091A
- Authority
- GB
- United Kingdom
- Prior art keywords
- moderator
- concrete
- graphite
- pedestal
- fuel
- 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
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/10—Means for supporting the complete structure
-
- 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
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
1,132,091. Moderator structures. ENGLISH ELECTRIC CO. Ltd. 9 June, 1966 [11 June, 1965], No. 24794/65. Heading G6C. In a nuclear reactor, the graphite moderator is mounted within a prestressed, cylindrical, concrete pressure vessel. To prevent misalignment of the fuel element channels in the moderator, and the standpipes in the vessel, due to dimension changes in the concrete, each vertical column of graphite blocks in the moderator is supported on a pedestal rigidly secured in the concrete. Each channel contains a graphite tube which holds the fuel and which is supported on a mounting within the pedestal. The base of each pedestal may be cooled by the pressure vessel cooling system. Spaces between the columns are provided to permit Wigher growth, graphite reflector blocks surround the core and radial restraint bars are mounted circumferentially between the moderator and concrete. Thermally induced dimension changes in the fuel channel tubing are accommodated by flexible bellows. The coolant gas may perform either a single or double pass along the channels.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB24794/65A GB1132091A (en) | 1965-06-11 | 1965-06-11 | Nuclear reactors |
FR63004A FR1484855A (en) | 1965-06-11 | 1966-05-26 | Nuclear reactor |
CH773066A CH444982A (en) | 1965-06-11 | 1966-05-27 | Nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB24794/65A GB1132091A (en) | 1965-06-11 | 1965-06-11 | Nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1132091A true GB1132091A (en) | 1968-10-30 |
Family
ID=10217335
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB24794/65A Expired GB1132091A (en) | 1965-06-11 | 1965-06-11 | Nuclear reactors |
Country Status (2)
Country | Link |
---|---|
CH (1) | CH444982A (en) |
GB (1) | GB1132091A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4259156A (en) * | 1977-02-07 | 1981-03-31 | Kraftwerk Union Aktiengesellschaft | Device for coupling pipelines in reactor pressure vessels, preferably the pipelines of the feedwater manifold |
-
1965
- 1965-06-11 GB GB24794/65A patent/GB1132091A/en not_active Expired
-
1966
- 1966-05-27 CH CH773066A patent/CH444982A/en unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4259156A (en) * | 1977-02-07 | 1981-03-31 | Kraftwerk Union Aktiengesellschaft | Device for coupling pipelines in reactor pressure vessels, preferably the pipelines of the feedwater manifold |
Also Published As
Publication number | Publication date |
---|---|
CH444982A (en) | 1967-10-15 |
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