GB984692A - Improvements in nuclear reactor installations - Google Patents
Improvements in nuclear reactor installationsInfo
- Publication number
- GB984692A GB984692A GB24763/61A GB2476361A GB984692A GB 984692 A GB984692 A GB 984692A GB 24763/61 A GB24763/61 A GB 24763/61A GB 2476361 A GB2476361 A GB 2476361A GB 984692 A GB984692 A GB 984692A
- Authority
- GB
- United Kingdom
- Prior art keywords
- gas
- reactor
- fuel
- graphite
- pressure vessel
- 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
- G21C1/322—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 above the core
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (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
984,692. Reactors. BABCOCK & WILCOX Ltd. July 7, 1961 [July 8, 1960], No. 24763/61. Heading G4G. In a gas cooled nuclear reactor circulation of the gas is effected, without a pump, by thermally induced gas flow through vertical ducting connecting the reactor pressure vessel with a heat exchange chamber above it. As shown, the reactor core 1 is cooled by the vertical flow of gas through channels 101, up duct 7 to pressure vessel 5 containing steam generator 4. The gas when cooled at 5 moves down through the annular space 108 to the lower pressure vessel space 110. The gas may be nitrogen, helium, or carbon dioxide at high pressure, and the reactor core is graphite with graphite-cased uranium oxide or carbide fuel elements. The plant is mounted in the ground within the vertical shaft 3. The heat release rate of the core is adjusted by control of the throttling valve 8 in the gas circuit. An automatic safety device directs the steam generated at 4 to a receiver when radio-active contaminations is detected. The gas in container 5 may be caused to recirculate round or by-pass the generator 4. To assist in the rapid removal of heat from the tube 7 at shut-down, cooling ducts may be arranged concentrically about 7. In an alternative reactor construction, not shown, the fuel is in the form of a mass of graphite spheres encasing fissile and fertile material held in a container of moderating material. As fresh fuel is added the resistance to coolant gas flow increases. This is allowed for by admitting gas to the fuel mass at progressively higher levels.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DED0033741 | 1960-07-08 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB984692A true GB984692A (en) | 1965-03-03 |
Family
ID=7041868
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB24763/61A Expired GB984692A (en) | 1960-07-08 | 1961-07-07 | Improvements in nuclear reactor installations |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB984692A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2767981A4 (en) * | 2011-10-14 | 2015-06-17 | Mitsubishi Heavy Ind Ltd | High-temperature gas reactor steam generator system |
-
1961
- 1961-07-07 GB GB24763/61A patent/GB984692A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2767981A4 (en) * | 2011-10-14 | 2015-06-17 | Mitsubishi Heavy Ind Ltd | High-temperature gas reactor steam generator system |
US9959945B2 (en) | 2011-10-14 | 2018-05-01 | Mitsubishi Heavy Industries, Ltd. | High temperature gas cooled reactor steam generation system |
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