GB1072512A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB1072512A GB1072512A GB25533/64A GB2553364A GB1072512A GB 1072512 A GB1072512 A GB 1072512A GB 25533/64 A GB25533/64 A GB 25533/64A GB 2553364 A GB2553364 A GB 2553364A GB 1072512 A GB1072512 A GB 1072512A
- Authority
- GB
- United Kingdom
- Prior art keywords
- concrete
- heat exchangers
- exchangers
- june
- core
- 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
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
- F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Chemical & Material Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
1,072,512. Cooling reactors. BABCOCK & WILCOX Ltd. June 21, 1965 [June 19, 1964], No. 25533/64. Heading G6C. The core of a gas cooled nuclear reactor is mounted together with heat exchangers within a concrete pressure vessel. An inverted capshaped biological shield separates the core and heat exchangers. Water is supplied to the exchangers by pipes through the concrete and emerges as steam through further piping. Provision is made at the heat exchangers to accommodate movements due to thermally induced dimension changes. The gas ducts between the exchangers and the biological shield include flexible bellow-type couplings. Similarly, the water and steam tubes include flexible bellows between the concrete vessel walls and the heat exchangers. In addition, each heat exchanger is supported from the vessel wall by a ball or roller and groove mounting. The gas pumps are mounted within bores in the concrete wall.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB25533/64A GB1072512A (en) | 1964-06-19 | 1964-06-19 | Improvements in or relating to nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB25533/64A GB1072512A (en) | 1964-06-19 | 1964-06-19 | Improvements in or relating to nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1072512A true GB1072512A (en) | 1967-06-21 |
Family
ID=10229220
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB25533/64A Expired GB1072512A (en) | 1964-06-19 | 1964-06-19 | Improvements in or relating to nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1072512A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2501830A1 (en) * | 1981-03-13 | 1982-09-17 | Stein Industrie | Indirect heat exchange system for nuclear reactor - with expansion vessels and circulation pumps grouped together, and separator balloons and water and steam collectors grouped together |
-
1964
- 1964-06-19 GB GB25533/64A patent/GB1072512A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2501830A1 (en) * | 1981-03-13 | 1982-09-17 | Stein Industrie | Indirect heat exchange system for nuclear reactor - with expansion vessels and circulation pumps grouped together, and separator balloons and water and steam collectors grouped together |
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