GB1423069A - Nuclear reactor installations - Google Patents
Nuclear reactor installationsInfo
- Publication number
- GB1423069A GB1423069A GB3887073A GB3887073A GB1423069A GB 1423069 A GB1423069 A GB 1423069A GB 3887073 A GB3887073 A GB 3887073A GB 3887073 A GB3887073 A GB 3887073A GB 1423069 A GB1423069 A GB 1423069A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- vessel
- coolant
- vessels
- run
- 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
- 238000009434 installation Methods 0.000 title abstract 2
- 239000002826 coolant Substances 0.000 abstract 8
- 238000005192 partition Methods 0.000 abstract 2
- 238000001816 cooling Methods 0.000 abstract 1
- 239000007788 liquid Substances 0.000 abstract 1
- 238000012423 maintenance Methods 0.000 abstract 1
Classifications
-
- 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
- G21C15/24—Promoting flow of the coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
-
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
1423069 Cooling nuclear reactors INTERATOM INTERNATIONALE ATOMREAKTORBAU GmbH 16 Aug 1973 [16 Aug 1972] 38870/73 Heading G6C In a nuclear reactor installation (e.g. employing a liquid sodium-cooled, fast reactor) heatexchangers are enclosed in secondary vessels disposed around the reactor bessel, coolant is conveyed between the reactor and secondary vessels by separate ducts forming hot and cold runs, and each secondary vessel is internally divided, by a partition, into two compartments into one of which the hot run opens and into the other of which the cold run opens, the partition affording apertures through which the heatexchangers are suspended. As shown, a cold run 10, provided by a pipe conveying coolant from the pressure side of a pump 4, leads to a core inlet plenum in reactor vessel 1 from a secondary vessel 2 housing heatexchangers 6. A hot run 12, provided by a suction pipe, leads from above the reactor core 3 to the secondary vessel 2 where the hot and cold coolant is maintained separate by a flow apron 9 through apertures of which the heat-exchangers are suspended from a respective shield plug 22. In order to compensate for thermal expansion in the pipes, each run 10, 12 extends, intermediate the vessels 1, 2, to a location above the top neutron shield 13 where the pipes are formed with loops. Gas spaces above the normal coelant levels 7, 8 in the vessels 1, 2 are connected by pressure-equalizing pipes 19. The vessels 1, 2 are surrounded by respective outer containers 17, 18 dimensioned to contain any leakage coolant and, in the instance of rupture of vessel 1, to ensure maintenance of a minimum coolant level 30 in vessel 1. Heated gas can be blown into the interspaces between vessels 1, 17 and 2, 18 for reactor start-up. To prevent all coolant from being withdrawn from vessel 1 in any circumstance, the runs 10, 12 are interconnected, in the region of the loops, by a small diameter pipe 31 which prevents siphon effects. This pipe may include a flow diode to restrict coolant by-pass flow during normal reactor operation. Inlets to the hot run 12 are disposed above the reactor vessel minimum coolant level 30.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2240067A DE2240067C3 (en) | 1972-08-16 | 1972-08-16 | Nuclear power plant in a decentralized compact design |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1423069A true GB1423069A (en) | 1976-01-28 |
Family
ID=5853599
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3887073A Expired GB1423069A (en) | 1972-08-16 | 1973-08-16 | Nuclear reactor installations |
Country Status (4)
Country | Link |
---|---|
JP (1) | JPS4946090A (en) |
DE (1) | DE2240067C3 (en) |
FR (1) | FR2196506B1 (en) |
GB (1) | GB1423069A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US11798697B2 (en) * | 2020-08-17 | 2023-10-24 | Terrapower, Llc | Passive heat removal system for nuclear reactors |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5352896A (en) * | 1976-10-22 | 1978-05-13 | Power Reactor & Nuclear Fuel Dev Corp | Liquid metal cooled nuclear reactor of cooling tank separately installed type |
DE2812124A1 (en) * | 1978-03-20 | 1979-09-27 | Interatom | NUCLEAR ENERGY SYSTEM IN A LOOP ARRANGEMENT |
GB2090042B (en) * | 1980-12-22 | 1984-04-26 | Westinghouse Electric Corp | Improved configuration for loop-type liquid metal fast breeder reactor |
FR2498365B1 (en) * | 1981-01-20 | 1986-08-29 | Commissariat Energie Atomique | NUCLEAR REACTOR COOLED BY A LIQUID METAL AND HAVING A THICK SLAB WITH HOUSING |
DE3334821A1 (en) * | 1983-09-26 | 1985-05-15 | INTERATOM GmbH, 5060 Bergisch Gladbach | CORE POWER PLANT WITH SIMPLIFIED LEAK PROTECTION OF THE COOLANT CIRCUIT |
EP0162956A3 (en) * | 1984-02-21 | 1988-01-07 | Stone & Webster Engineering Corporation | Modular liquid metal nuclear reactor |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1564054C3 (en) * | 1966-12-15 | 1975-03-13 | Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe | Nuclear reactor |
DE1815046A1 (en) * | 1968-12-17 | 1970-06-25 | Interatom | Pipeline from reactor shell to heat - exchanger for a liquid cooled nuclear rct |
DE2013586C3 (en) * | 1970-03-21 | 1975-11-27 | Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe | Liquid-cooled nuclear reactor |
-
1972
- 1972-08-16 DE DE2240067A patent/DE2240067C3/en not_active Expired
-
1973
- 1973-08-10 JP JP48089950A patent/JPS4946090A/ja active Pending
- 1973-08-13 FR FR7329574A patent/FR2196506B1/fr not_active Expired
- 1973-08-16 GB GB3887073A patent/GB1423069A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US11798697B2 (en) * | 2020-08-17 | 2023-10-24 | Terrapower, Llc | Passive heat removal system for nuclear reactors |
Also Published As
Publication number | Publication date |
---|---|
JPS4946090A (en) | 1974-05-02 |
DE2240067C3 (en) | 1981-11-12 |
DE2240067A1 (en) | 1974-02-28 |
FR2196506A1 (en) | 1974-03-15 |
FR2196506B1 (en) | 1978-07-13 |
DE2240067B2 (en) | 1981-01-29 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |