GB972474A - Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors - Google Patents
Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactorsInfo
- Publication number
- GB972474A GB972474A GB8403/62A GB840362A GB972474A GB 972474 A GB972474 A GB 972474A GB 8403/62 A GB8403/62 A GB 8403/62A GB 840362 A GB840362 A GB 840362A GB 972474 A GB972474 A GB 972474A
- Authority
- GB
- United Kingdom
- Prior art keywords
- gas
- channel
- ports
- strips
- valve
- 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
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
-
- 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)
- Details Of Valves (AREA)
Abstract
972,474. Fuelling reactors. FAIREY ENGINEERING Ltd. June 5,1963 [March 5, 19621, No. 8403/62. Heading G6C. In order to prevent blow out of the fuel elements remaining in a reactor core channel after the majority of the elements in that charnel have been removed by a grab, the upward flow of coolant gas through the channel is automatically reduced by a valve responsive to the gas temperature. The valve is mounted at the lower end of a charge shoot adapted for connection to the channel and controls the flow from the channel into the space enclosed by the pressure vessel. At the normal working temperature of the gas in the channel corresponding to a fully loaded channel the valve is fully open but it closes progressively as the temperature drops as the fuel elements are removed. As shown, the lower end of a charge shoot 13 has a tubular extension 10 provided with ports 27 and surrounded by a fixed sleeve 15 having ports 25. Three annular members 20, 23, 24 are secured to the sleeve 15 and each annular member has four arcuate bimetallic strips 30 anchored thereto by rivets 32. The other ends of the strips 30 of each group are riveted at 33 to a ring 28 of L-section. At the normal working temperature of the gas the strips 30 are deflected so that the rings 28 are raised as seen in the right-hand half of Fig. 1 and the ports 25 are not obstructed. On cooling of the gas, however, the strips unflex so that the rings 28 drop and substantially close the ports 25 as shown in the left hand half of Fig. 1
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB8403/62A GB972474A (en) | 1962-03-05 | 1962-03-05 | Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB8403/62A GB972474A (en) | 1962-03-05 | 1962-03-05 | Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB972474A true GB972474A (en) | 1964-10-14 |
Family
ID=9851880
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB8403/62A Expired GB972474A (en) | 1962-03-05 | 1962-03-05 | Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB972474A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4206658A1 (en) * | 1992-03-03 | 1993-09-09 | Siemens Ag | SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK |
DE4206660A1 (en) * | 1992-03-03 | 1993-09-09 | Siemens Ag | SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK |
-
1962
- 1962-03-05 GB GB8403/62A patent/GB972474A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4206658A1 (en) * | 1992-03-03 | 1993-09-09 | Siemens Ag | SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK |
DE4206660A1 (en) * | 1992-03-03 | 1993-09-09 | Siemens Ag | SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK |
US5517538A (en) * | 1992-03-03 | 1996-05-14 | Siemens Aktiengesellschaft | Safety device protecting a nuclear reactor pressure vessel against overpressure failure |
US5526385A (en) * | 1992-03-03 | 1996-06-11 | Siemens Aktiengesellschaft | Safety device protecting against overpressure failure of a nuclear reactor pressure vessel |
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