GB1013544A - Improvements in gas-cooled nuclear reactors - Google Patents
Improvements in gas-cooled nuclear reactorsInfo
- Publication number
- GB1013544A GB1013544A GB24497/62A GB2449762A GB1013544A GB 1013544 A GB1013544 A GB 1013544A GB 24497/62 A GB24497/62 A GB 24497/62A GB 2449762 A GB2449762 A GB 2449762A GB 1013544 A GB1013544 A GB 1013544A
- Authority
- GB
- United Kingdom
- Prior art keywords
- moderator
- fuel
- heat
- fuel elements
- 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
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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)
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
1,013,544. Cooling arrangements for gascooled nuclear reactors. BABCOCK & WILCOX Ltd. June 26, 1962 [June 26, 1961], No. 24497/62. Heading G6C. A gas-cooled nuclear reactor having fuel elements disposed in channels in moderating material has solid heat conducting means arranged to transfer heat from the fuel elements to the moderator, which is arranged to be cooled during the operation of the reactor, the thermal conducting properties of the solid heat-conducting means being such that, upon shut-down of the reactor, heat is transferred from the fuel elements to the moderator at a rate approximately equal to the rate of heat generation in the fuel elements as a result of the disintegration of radio-active fission products after the chain reaction has ceased. The principle of the arrangement is illustrated by Fig. 1, where heat generated in nuclear fuel 1 is conducted mainly to the passing coolant indicated by arrows 2 and partly through heatconducting body 3 in the direction of arrows " q " to the moderator 4. The moderator 4 gives off this heat and any other produced in the moderator to coolant stream 5. Coolant streams 2 and 5 may be separate systems or they may be a common circuit as indicated by arrow 6, where the coolant gas first cools the moderator before passing over the fuel element. If the cooling system fails and the reactor is shut down, the heat generated in 1 by radioactive decay is conducted away from the fuel elements by bodies 3 and is stored in the moderator. Figs. 2 to 8 (not shown) illustrate various embodiments of this principle. Figs. 2 and 3 illustrate a liquid moderated reactor with separate moderator and fuel element cooling systems, the fuel element being enclosed in a heat-conducting material which is in close contact with the fuel channel wall. Fig. 4 illustrates a fuel element, having central cooling channels, but which is insulated externally from the coolant stream, thus providing separate channels for cooling the moderator and the fuel elements, the heat conducting means being fins which are insulated from the coolant stream but in contact with the moderator. Figs. 5 and 6 illustrate dished fuel elements with central apertures, the fuel element being equipped with spaced radial flanges which contact the moderator and Figs. 7 and 8 show fuel elements which are frusto-conical shells supported on flanges in grooves in the moderator. In the last two embodiments the construction of the fuel elements provides the passages for coolant flow, and, if desired, the radial surfaces of the fuel elements may be equipped with a helical fin extending coaxially of the central aperture to induce spiral flow of the coolant over the surface. The flanges mentioned above serve as the heat conducting means.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DED0036406 | 1961-06-26 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1013544A true GB1013544A (en) | 1965-12-15 |
Family
ID=7043096
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB24497/62A Expired GB1013544A (en) | 1961-06-26 | 1962-06-26 | Improvements in gas-cooled nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1013544A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2218255A (en) * | 1988-05-03 | 1989-11-08 | Rolls Royce & Ass | High power fast reactor |
CN111063461A (en) * | 2019-12-31 | 2020-04-24 | 中国科学院合肥物质科学研究院 | Solid critical device |
-
1962
- 1962-06-26 GB GB24497/62A patent/GB1013544A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2218255A (en) * | 1988-05-03 | 1989-11-08 | Rolls Royce & Ass | High power fast reactor |
CN111063461A (en) * | 2019-12-31 | 2020-04-24 | 中国科学院合肥物质科学研究院 | Solid critical device |
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