GB908456A - Improvements in or relating to nuclear reactor control elements - Google Patents
Improvements in or relating to nuclear reactor control elementsInfo
- Publication number
- GB908456A GB908456A GB16445/60A GB1644560A GB908456A GB 908456 A GB908456 A GB 908456A GB 16445/60 A GB16445/60 A GB 16445/60A GB 1644560 A GB1644560 A GB 1644560A GB 908456 A GB908456 A GB 908456A
- Authority
- GB
- United Kingdom
- Prior art keywords
- nuclear reactor
- neutron absorbing
- boron steel
- neutron
- relating
- 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
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/022—Reactor fuses
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Particle Accelerators (AREA)
Abstract
908,456. Nuclear reactor control rods. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. May 5, 1961 [May 10, 1960], No. 16445/60. Class 39 (4). A control device for a pressurized gas-cooled nuclear reactor comprises a neutron absorbing body 5 housed within a neutron absorbing body 4 in a container 3 in a vertical channel in the reactor core, and means for releasing the body 5 so that it falls under gravity, thus increasing the neutron absorption capacity of the device. In the device shown, on a sudden reduction of coolant gas pressure, gas escapes more quickly through holes 22, 23 than through hole 21, thus creating a pressure difference across diaphragm 11 which moves and lowers plug 13, allowing boron steel shot 5 to fall out of boron steel tube 4 into tube 18. Other neutron absorbing elements referred to are cadmium, mercury and rare earths.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB16445/60A GB908456A (en) | 1960-05-10 | 1960-05-10 | Improvements in or relating to nuclear reactor control elements |
DEU8006A DE1208424B (en) | 1960-05-10 | 1961-05-09 | Shutdown device for gas-cooled nuclear reactors |
FR861314A FR1289107A (en) | 1960-05-10 | 1961-05-09 | Regulating device for nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB16445/60A GB908456A (en) | 1960-05-10 | 1960-05-10 | Improvements in or relating to nuclear reactor control elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB908456A true GB908456A (en) | 1962-10-17 |
Family
ID=10077449
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB16445/60A Expired GB908456A (en) | 1960-05-10 | 1960-05-10 | Improvements in or relating to nuclear reactor control elements |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE1208424B (en) |
GB (1) | GB908456A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4104121A (en) * | 1972-06-02 | 1978-08-01 | Groupement Atomique Alsacienne Atlantique | Solid absorbent safety device for a nuclear reactor |
FR2394147A1 (en) * | 1977-06-10 | 1979-01-05 | Combustion Eng | DEVICE FOR RETAINING, RELEASING AND REPLACING NEUTRON ABSORPTION MASSES |
US4407774A (en) * | 1976-07-23 | 1983-10-04 | Kernforschungszentrum Karlsruhe G.M.B.H. | Method for preventing dangerous hydrogen accumulation in nuclear reactor containments |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1052000B (en) * | 1957-12-13 | 1959-03-05 | Siemens Ag | Shutdown device for liquid-cooled nuclear reactors |
-
1960
- 1960-05-10 GB GB16445/60A patent/GB908456A/en not_active Expired
-
1961
- 1961-05-09 DE DEU8006A patent/DE1208424B/en active Pending
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4104121A (en) * | 1972-06-02 | 1978-08-01 | Groupement Atomique Alsacienne Atlantique | Solid absorbent safety device for a nuclear reactor |
US4407774A (en) * | 1976-07-23 | 1983-10-04 | Kernforschungszentrum Karlsruhe G.M.B.H. | Method for preventing dangerous hydrogen accumulation in nuclear reactor containments |
FR2394147A1 (en) * | 1977-06-10 | 1979-01-05 | Combustion Eng | DEVICE FOR RETAINING, RELEASING AND REPLACING NEUTRON ABSORPTION MASSES |
Also Published As
Publication number | Publication date |
---|---|
DE1208424B (en) | 1966-01-05 |
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