GB1434384A - Gas-cooled nuclear reactor installations - Google Patents
Gas-cooled nuclear reactor installationsInfo
- Publication number
- GB1434384A GB1434384A GB3313473A GB3313473A GB1434384A GB 1434384 A GB1434384 A GB 1434384A GB 3313473 A GB3313473 A GB 3313473A GB 3313473 A GB3313473 A GB 3313473A GB 1434384 A GB1434384 A GB 1434384A
- Authority
- GB
- United Kingdom
- Prior art keywords
- vessel
- tank
- steam
- core
- water
- 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
- G21C9/016—Core catchers
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1434384 Nuclear reactors SIEMENS AG 11 July 1973 [14 July 1972] 33134/73 Heading G6C In a nuclear reactor installation, a spray system has outlets within the reactor pressure vessel for the purpose of cooling melted core material. The reactor is a gas- (e.g. helium) cooled fast breeder. In one embodiment (Fig. 1) fuel elements are secured by means of a holding device 10 comprising tubes 12 through which coolant gas normally is fed towards the core 4. The coolant circulates within the concrete pressure vessel 2, as indicated by arrows 16, so as to pass in heatexchange relation with a steam-generator 15. The lower part of the shield 3 within the vessel 2 forms a tank 20 which receives core material, should this fuse, and prevents accumulation of a critical size. Water is sprayed into the vessel 2 via the tubes 12 in the event of core meltdown, the steam generated passing to the generator 15; a one-way valve ensures continuance of the (arrowed) flow pattern. A larger tank 25 is provided to receive debris should the core melt its way through the base of tank 20 and the vessel wall supporting the latter; additional cooling means may be provided in tank 25. Should steam not be routed through the steamgenerator 15 as described, it may be released into the interior of the steel containment 1 and heat removed therefrom by water emanating from an external sprinkler system 28. In another embodiment (Fig. 2) water can be sprayed into tank 20 from lines 30, 31 within the vessel 2. After passing through the steamgenerator 15, excess steam can pass to the exterior of the vessel 2 via an aperture 36 to give up heat to the surrounding steel containment.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2234744A DE2234744A1 (en) | 1972-07-14 | 1972-07-14 | NUCLEAR REACTOR |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1434384A true GB1434384A (en) | 1976-05-05 |
Family
ID=5850688
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3313473A Expired GB1434384A (en) | 1972-07-14 | 1973-07-11 | Gas-cooled nuclear reactor installations |
Country Status (4)
Country | Link |
---|---|
DE (1) | DE2234744A1 (en) |
FR (1) | FR2193232A1 (en) |
GB (1) | GB1434384A (en) |
IT (1) | IT992614B (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5930319A (en) * | 1995-06-27 | 1999-07-27 | Siemens Aktiengesellschaft | Nuclear reactor with a core melt propagation space provided with a coolant conduit leading to a coolant reservoir |
CN114728337A (en) * | 2019-11-22 | 2022-07-08 | 法国电力公司 | Solid metal component and method for producing a solid metal component |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2653258C2 (en) * | 1976-11-24 | 1985-02-28 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for reducing the dangers that may arise as a result of an accident through the melting of a nuclear reactor core, as well as an arrangement for carrying out the process |
-
1972
- 1972-07-14 DE DE2234744A patent/DE2234744A1/en active Pending
-
1973
- 1973-07-11 IT IT26456/73A patent/IT992614B/en active
- 1973-07-11 GB GB3313473A patent/GB1434384A/en not_active Expired
- 1973-07-13 FR FR7325706A patent/FR2193232A1/fr not_active Withdrawn
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5930319A (en) * | 1995-06-27 | 1999-07-27 | Siemens Aktiengesellschaft | Nuclear reactor with a core melt propagation space provided with a coolant conduit leading to a coolant reservoir |
CN114728337A (en) * | 2019-11-22 | 2022-07-08 | 法国电力公司 | Solid metal component and method for producing a solid metal component |
Also Published As
Publication number | Publication date |
---|---|
DE2234744A1 (en) | 1974-01-31 |
IT992614B (en) | 1975-09-30 |
FR2193232A1 (en) | 1974-02-15 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US3182002A (en) | Liquid cooled nuclear reactor with improved heat exchange arrangement | |
US3151034A (en) | Consolidated nuclear steam generator arrangement | |
US3677892A (en) | Collecting device for cooling reactor core fragments in a fast breeder reactor | |
ES381826A1 (en) | Nuclear reactor core and shroud | |
US4464333A (en) | Molten core retention and solidification apparatus | |
GB785528A (en) | Nuclear reactor plant | |
GB1212299A (en) | Nuclear reactor containment system | |
US6195405B1 (en) | Gap structure for nuclear reactor vessel | |
US4752439A (en) | Safety enclosure cooling system for gas cooled high temperature reactors | |
GB2030347A (en) | Nuclear Reactor Containment | |
US3080308A (en) | Simplified sodium graphite reactor system | |
JP2000504119A (en) | Clearance structure for reactor vessel | |
GB915491A (en) | Modular core units for a nuclear reactor | |
GB1434384A (en) | Gas-cooled nuclear reactor installations | |
GB1431999A (en) | Nuclear reactor installations | |
US3052615A (en) | Nuclear flash steam generator | |
US4072560A (en) | Pressurized-water reactor pressure vessel emergency core coolant connection arrangement | |
US4118278A (en) | Nuclear reactor insulation and preheat system | |
US3635792A (en) | Refuelling means for nuclear reactors | |
GB2157880A (en) | An improved nuclear reactor plant construction | |
US3802962A (en) | Neutron flux measurement installation for liquid-cooled nuclear reactors | |
GB875813A (en) | Improvements in or relating to nuclear reactor installations | |
ES8702021A1 (en) | Pressurized water reactor plant comprising a pressurized pool. | |
JP2016166833A (en) | Reactor container and construction method of reactor container | |
GB868678A (en) | Improvements in or relating to nuclear reactors |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |