GB1003827A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- GB1003827A GB1003827A GB4456/63A GB445663A GB1003827A GB 1003827 A GB1003827 A GB 1003827A GB 4456/63 A GB4456/63 A GB 4456/63A GB 445663 A GB445663 A GB 445663A GB 1003827 A GB1003827 A GB 1003827A
- Authority
- GB
- United Kingdom
- Prior art keywords
- chamber
- water
- reactor
- passages
- coolant
- 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
- G21C7/00—Control of nuclear reaction
- G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
-
- 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
- G21C1/09—Pressure regulating arrangements, i.e. pressurisers
-
- 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
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
1,003,827. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY LONDON. Jan. 21, 1964 [Feb. 4, 1963], No. 4456/63. Heading G6C. A water-cooled reactor has vertical passages for delivery of coolant to a plenum chamber below the reactor core, said passages extending through a chamber defined by the core and the reactor vessel walls, the cross-section of the passages being small compared with said chamber. The boiling water reactor described includes a baffle 13 containing fuel tubes 12 through which a primary coolant circulates, and is surrounded by a water-filled reflecting region 24 and a pressurizer chamber 29. A steam separator 46 passes steam through an outlet 43, and heated water through an outlet 47. Pressurizer 38 is connected to primary coolant feed pumps 37. A mixture of cold feed water and recirculated hot water enters the pressure vessel at 48 and passes through holes 51 into an annular chamber 49. The vertical passages 25 carry coolant from the chamber 49 to the inlet plenum chamber 23. A small amount of water flows from the chamber 29 through holes 52 and 14 to the inlet plenum chamber 23. By using a small flow cross-section compared with the cross-sections of chambers 29 and 24, re-circulation time of the hot water is reduced by approximately 30%, resulting in improved power level control stability. Specification 969,814 is referred to.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB4456/63A GB1003827A (en) | 1963-02-04 | 1963-02-04 | Nuclear reactor |
US340885A US3280004A (en) | 1963-02-04 | 1964-01-29 | Water cooled nuclear reactor with improved core and reflector recirculation system |
BE643359A BE643359A (en) | 1963-02-04 | 1964-02-04 |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB4456/63A GB1003827A (en) | 1963-02-04 | 1963-02-04 | Nuclear reactor |
BE643359A BE643359A (en) | 1963-02-04 | 1964-02-04 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1003827A true GB1003827A (en) | 1965-09-08 |
Family
ID=25655667
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB4456/63A Expired GB1003827A (en) | 1963-02-04 | 1963-02-04 | Nuclear reactor |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE643359A (en) |
GB (1) | GB1003827A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0057369A2 (en) * | 1981-01-29 | 1982-08-11 | Westinghouse Electric Corporation | Valve support arrangement for a pressurizer vessel in a nuclear power plant |
-
1963
- 1963-02-04 GB GB4456/63A patent/GB1003827A/en not_active Expired
-
1964
- 1964-02-04 BE BE643359A patent/BE643359A/xx unknown
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0057369A2 (en) * | 1981-01-29 | 1982-08-11 | Westinghouse Electric Corporation | Valve support arrangement for a pressurizer vessel in a nuclear power plant |
EP0057369A3 (en) * | 1981-01-29 | 1982-10-27 | Westinghouse Electric Corporation | Improved valve support arrangement for pressurizer in a nuclear power plant |
Also Published As
Publication number | Publication date |
---|---|
BE643359A (en) | 1964-08-04 |
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