GB795406A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB795406A GB795406A GB6836/56A GB683656A GB795406A GB 795406 A GB795406 A GB 795406A GB 6836/56 A GB6836/56 A GB 6836/56A GB 683656 A GB683656 A GB 683656A GB 795406 A GB795406 A GB 795406A
- Authority
- GB
- United Kingdom
- Prior art keywords
- coolant
- region
- liquid
- climbing film
- moderator
- 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
- G21C1/04—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
-
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
795,406. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. March 4, 1957 [March 5, 1956], No. 6836/56. Class 39(4). A nuclear reactor comprises fuel elements of such shape and dimensions as to provide a smooth continuous surface, a further continuous surface closely adjacent to said surface to define a passage capable of supporting a climbing film system when the reactor is in operation, and means for feeding coolant liquid to the lower end of the passage at such a pressure head and feed rate that a climbing film system is set up. Fig. 2 illustrates the behaviour of a coolant liquid as it passes upwardly through the annular space between a fuel element 12 and a coolant tube 1. In region A there is normal ebullition, and in region B discrete annular slugs of liquid 15 surround annular vapour slugs 16. In region C a climbing film system is set up with liquid films attached to the coolant tube 1 and to the fuel element 12 and vapour in the annular space between ; finally in region D there is a spray region where the films are disrupted. The onset of this spray condition should be avoided except where a ceramic type of fuel element is used over this region. Fig. 1 shows a reactor in which the climbing film region can occupy 60-80 per cent of the total height of the coolant tube and the spray region eliminated by choosing appropriate dimensions and by adjustment of the coolant pressure head and feed rate. The steam produced and the residual coolant liquid leave the coolant tubes at the top and the two phases are separated by individual separators 19. The bulk moderator fluid 8 and the coolant liquid are the same, e.g., water or heavy water, so that the separated liquid may be passed directly into the bulk of the moderator. The steam passes out of the pressure vessel to turbines 21 after which it is condensed and returned to the coolant header tank 10. In an alternative arrangement the coolant tubes 1 pass into a common header and thence to a single external cyclone separator ; this may be better if the coolant liquid is not the same as the moderator liquid.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB6836/56A GB795406A (en) | 1956-03-05 | 1956-03-05 | Improvements in or relating to nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB6836/56A GB795406A (en) | 1956-03-05 | 1956-03-05 | Improvements in or relating to nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB795406A true GB795406A (en) | 1958-05-21 |
Family
ID=9821640
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB6836/56A Expired GB795406A (en) | 1956-03-05 | 1956-03-05 | Improvements in or relating to nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB795406A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1183605B (en) * | 1960-02-12 | 1964-12-17 | Licentia Gmbh | Boiling water reactor with integral steam superheating |
DE1225314B (en) * | 1958-08-08 | 1966-09-22 | Atomic Energy Commission | Atomic nuclear reactor with two different pressure zones |
DE1275213B (en) * | 1966-12-22 | 1968-08-14 | Siemens Ag | Boiling water reactor in an integrated design |
CN114383933A (en) * | 2022-01-06 | 2022-04-22 | 西安交通大学 | High-temperature gas flow heat exchange safety pressure container |
-
1956
- 1956-03-05 GB GB6836/56A patent/GB795406A/en not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1225314B (en) * | 1958-08-08 | 1966-09-22 | Atomic Energy Commission | Atomic nuclear reactor with two different pressure zones |
DE1183605B (en) * | 1960-02-12 | 1964-12-17 | Licentia Gmbh | Boiling water reactor with integral steam superheating |
DE1275213B (en) * | 1966-12-22 | 1968-08-14 | Siemens Ag | Boiling water reactor in an integrated design |
CN114383933A (en) * | 2022-01-06 | 2022-04-22 | 西安交通大学 | High-temperature gas flow heat exchange safety pressure container |
CN114383933B (en) * | 2022-01-06 | 2023-06-13 | 西安交通大学 | High-temperature gas flowing heat exchange safety pressure vessel |
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