GB992033A - A boiling-water nuclear reactor installation - Google Patents
A boiling-water nuclear reactor installationInfo
- Publication number
- GB992033A GB992033A GB9136/62A GB913662A GB992033A GB 992033 A GB992033 A GB 992033A GB 9136/62 A GB9136/62 A GB 9136/62A GB 913662 A GB913662 A GB 913662A GB 992033 A GB992033 A GB 992033A
- Authority
- GB
- United Kingdom
- Prior art keywords
- steam
- vessel
- condenser
- reactor
- emergency
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- 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
-
- 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
-
- 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
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
992,033. Nuclear power plant. LICENTIA PATENT VERWALTUNGS-G.m.b.H. March 9, 1962 [March 14, 1961], No. 9136/62. Heading G6C. An emergency condenser installation for a liquid cooled nuclear reactor has, in addition to an emergency condenser, a steam collecting vessel dimensioned to receive the whole of the steam generated in the reactor in the period between the interruption of the discharge of steam to the turbine condenser and the bringing into service of the emergency condenser. This steam collecting vessel is a pressure vessel partially filled with cold water with atmospheric air above the water and nozzles to introduce the steam being provided in the vessel. If the discharge of steam from the superheater reactor 4 is shut off, then the connection to the steam collecting vessel 9 is established very quickly, but too much steam must be prevented from entering the vessel otherwise sudden cooling of the reactors 1 and 4 would ensue. Also when the emergency condenser 12 is able to operate the supply to the vessel 9 must cease and the steam directed to the condenser 12. Should the steam from reactor 1 to superheater 4 be interrupted then the connection between the reactor 1 and condenser 12 must be established very quickly, and the vessel 9 must be shut off.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DEL38429A DE1170563B (en) | 1961-03-14 | 1961-03-14 | Emergency condensation system for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB992033A true GB992033A (en) | 1965-05-12 |
Family
ID=7268271
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB9136/62A Expired GB992033A (en) | 1961-03-14 | 1962-03-09 | A boiling-water nuclear reactor installation |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE1170563B (en) |
GB (1) | GB992033A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3437557A (en) * | 1966-04-07 | 1969-04-08 | Asea Ab | Arrangement for preventing shutdown of a nuclear reactor plant when the load on a turbine driven thereby decreases suddenly |
EP0004167A2 (en) * | 1978-03-04 | 1979-09-19 | BROWN BOVERI REAKTOR GmbH | Apparatus for emergency cooling of a steam generator of a nuclear power plant |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1489950B1 (en) * | 1965-11-15 | 1970-01-29 | Kernforschung Gmbh Ges Fuer | Emergency condensation system for steam-cooled nuclear reactors |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1211537A (en) * | 1958-08-14 | 1960-03-16 | Commissariat Energie Atomique | Heat absorption device of a nuclear reactor in the event of shutdown or overpressure |
-
1961
- 1961-03-14 DE DEL38429A patent/DE1170563B/en active Pending
-
1962
- 1962-03-09 GB GB9136/62A patent/GB992033A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3437557A (en) * | 1966-04-07 | 1969-04-08 | Asea Ab | Arrangement for preventing shutdown of a nuclear reactor plant when the load on a turbine driven thereby decreases suddenly |
DE1526995B1 (en) * | 1966-04-07 | 1970-10-08 | Allmaenna Svenska Elek Ska Ag | Nuclear power plant |
EP0004167A2 (en) * | 1978-03-04 | 1979-09-19 | BROWN BOVERI REAKTOR GmbH | Apparatus for emergency cooling of a steam generator of a nuclear power plant |
EP0004167A3 (en) * | 1978-03-04 | 1979-10-03 | Babcock-Brown Boveri Reaktor Gmbh | Apparatus for emergency cooling of a steam generator of a nuclear power plant |
Also Published As
Publication number | Publication date |
---|---|
DE1170563B (en) | 1964-05-21 |
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