FR2254972A5 - Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam - Google Patents
Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steamInfo
- Publication number
- FR2254972A5 FR2254972A5 FR7344391A FR7344391A FR2254972A5 FR 2254972 A5 FR2254972 A5 FR 2254972A5 FR 7344391 A FR7344391 A FR 7344391A FR 7344391 A FR7344391 A FR 7344391A FR 2254972 A5 FR2254972 A5 FR 2254972A5
- Authority
- FR
- France
- Prior art keywords
- water
- secondary containment
- nuclear reactor
- mixers
- condense
- 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
- G21C9/004—Pressure suppression
- G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
-
- 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)
Abstract
System for protecting the secondary containment of a water cooled nuclear reactor from overpressure due to a release of steam from the main coolant circuits, uses a double secondary containment with cooled water in the space between. The steam/air mixture inside the inner secondary containment is taken to a variety of mixing devices below the surface of the water between the inner and outer secondary containment shells. Thus the risk of escape of primary radio-activated coolant is minimised.
Priority Applications (12)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7344391A FR2254972A5 (en) | 1973-12-12 | 1973-12-12 | Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam |
GB5185074A GB1463148A (en) | 1973-12-12 | 1974-11-29 | Liquid cooled nuclear reactors |
US05/529,095 US4022655A (en) | 1973-12-12 | 1974-12-03 | Device for limiting accidental pressure overloads in a nuclear reactor confinement structure |
BE151100A BE822887A (en) | 1973-12-12 | 1974-12-03 | DEVICE FOR LIMITING ACCIDENTAL OVERPRESSIONS IN A CONTAINMENT STRUCTURE OF A MUCLEAR REACTOR |
CH1600274A CH591142A5 (en) | 1973-12-12 | 1974-12-03 | |
NL7415804A NL7415804A (en) | 1973-12-12 | 1974-12-04 | DEVICE FOR RESTRICTING UNEXPECTED OVERPRINTS IN A CONNECTING CONSTRUCTION OF A NUCLEAR REACTOR. |
DE2457901A DE2457901C2 (en) | 1973-12-12 | 1974-12-06 | Safety device for limiting overpressure in the container of a water-cooled nuclear reactor |
CA215,635A CA1017468A (en) | 1973-12-12 | 1974-12-10 | Device for limiting accidental pressure overloads in a nuclear reactor confinement structure |
ES432791A ES432791A1 (en) | 1973-12-12 | 1974-12-11 | Device for limiting accidental pressure overloads in a nuclear reactor confinement structure |
IT70602/74A IT1027052B (en) | 1973-12-12 | 1974-12-11 | DEVICE FOR LIMITING ACCIDENTAL OVERPRESSURES IN A CONFINING TUBE STRUCTURE OF A NUCLEAR REACT |
SE7415641A SE398408B (en) | 1973-12-12 | 1974-12-12 | DEVICE FOR LIMITING UN INTENDED PRESSURE LOADS IN THE INCLUDING CONSTRUCTION OF A NUCLEAR REACTOR |
JP49143008A JPS5740998B2 (en) | 1973-12-12 | 1974-12-12 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7344391A FR2254972A5 (en) | 1973-12-12 | 1973-12-12 | Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam |
Publications (1)
Publication Number | Publication Date |
---|---|
FR2254972A5 true FR2254972A5 (en) | 1975-07-11 |
Family
ID=9129122
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7344391A Expired FR2254972A5 (en) | 1973-12-12 | 1973-12-12 | Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE822887A (en) |
FR (1) | FR2254972A5 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2344098A1 (en) * | 1976-03-08 | 1977-10-07 | Kraftwerk Union Ag | EVACUATION OR BLEEDING DEVICE INTENDED TO LIMIT OVERPRESSURES IN NUCLEAR POWER PLANTS, ESPECIALLY IN NUCLEAR POWER PLANTS WITH BOILING WATER |
-
1973
- 1973-12-12 FR FR7344391A patent/FR2254972A5/en not_active Expired
-
1974
- 1974-12-03 BE BE151100A patent/BE822887A/en not_active IP Right Cessation
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2344098A1 (en) * | 1976-03-08 | 1977-10-07 | Kraftwerk Union Ag | EVACUATION OR BLEEDING DEVICE INTENDED TO LIMIT OVERPRESSURES IN NUCLEAR POWER PLANTS, ESPECIALLY IN NUCLEAR POWER PLANTS WITH BOILING WATER |
Also Published As
Publication number | Publication date |
---|---|
BE822887A (en) | 1975-04-01 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES361693A1 (en) | Nuclear reactor containment system for metropolitan sites | |
GB1178380A (en) | Safety Cooling System for a Nuclear Reactor. | |
GB965536A (en) | Improvements in and relating to nuclear reactors | |
ES401704A1 (en) | Thermal shield of a nuclear reactor | |
FR2254973A5 (en) | Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam | |
FR2254972A5 (en) | Water cooled nuclear reactor twin secondary containment - the intervening space filled with water and mixers to condense leakage steam | |
GB862624A (en) | Improvements in or relating to nuclear reactor installations | |
GB1032221A (en) | Improvements in nuclear reactors | |
US2846872A (en) | Leakage testing method | |
GB1003826A (en) | Improvements in or relating to nuclear reactors | |
GB1273559A (en) | Improvements in liquid cooled nuclear reactor pressure vessel | |
FR2140606A1 (en) | Irradiated fuel transport flask - incorporating depleted uranium and water shielding | |
CA992000A (en) | Steam power plant for nuclear power stations having pressurized water reactors | |
FR2232042A1 (en) | Reactor vessel integral external seal membrane - creating containment for water shielding for vessel access | |
JPS52100077A (en) | Pressure suppression device | |
FR2114258A5 (en) | Nuclear reactor for indirect heating cycle - with heat exchange chamber at lower pressure than core chamber | |
GB1011639A (en) | Integral nuclear reactor | |
FR2177700A1 (en) | Nuclear power station damage control - with containment system for leaking coolant | |
GB845456A (en) | Improvements in or relating to fuel element discharge systems for nuclear reactors | |
ES359781A1 (en) | Nuclear Reactor Containment Vessels and Methods of Constructing Such Vessels. | |
JPS5268699A (en) | Boiled water type reactor | |
FR2237279A1 (en) | Prevention of environmental pollution by radioactive emission - from a nuclear power plant | |
NL6816145A (en) | Nuclear reactor with high pressure gas cooling | |
JPS5346596A (en) | Emergency measures for nuclear reactor cooling system | |
JPS5354691A (en) | Core cooling system of nuclear reactor |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |