GB1448071A - Nuclear reactor installations - Google Patents
Nuclear reactor installationsInfo
- Publication number
- GB1448071A GB1448071A GB869974A GB869974A GB1448071A GB 1448071 A GB1448071 A GB 1448071A GB 869974 A GB869974 A GB 869974A GB 869974 A GB869974 A GB 869974A GB 1448071 A GB1448071 A GB 1448071A
- Authority
- GB
- United Kingdom
- Prior art keywords
- core
- auxiliary coolant
- reactor
- coolant
- trough
- 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
- 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
1448071 Nuclear reactors SIEMENS AG 26 Feb 1974 [30 March 1973] 8699/74 Heading G6C In a nuclear reactor installation, especially one including a PWR, there is provided a first auxiliary coolant supply system whereby auxiliary coolant can be introduced into a steam generator, and/or a second auxiliary coolant supply system whereby auxiliary coolant can be introduced into the reactor core. In the embodiment shown, auxiliary coolant from a variety of alternative sources (such as a sump 19, fuel storage tank 60, pressurizer 30 and header tank 40) can be introduced, as appropriate to circumstances, via conduits and non-return valves, into: (1) an outlet chamber 12 of steam generator 10-through spray means 57-so as to enter "cold" legs 14, 14<SP>1</SP> which lead the coolant to the pressure vessel 1; (2) a "hot" leg 9-so as to debouch into a trough 27 above the core 5, the trough 27 having apertures for directing coolant against the inner surface of core container 4; (3) the space above the core, via pipes having spray apertures 55a directed towards the wall of an above-core structure 6; (4) into the core, via pipes 52; and (5) into the reactor building, via spray means 68. Water from tank 40 has to pass through a container 42 containing boric acid solution for effecting reduction of reactivity of the reactor. A plug-andsocket connection 51 enables easy removal of the pressure vessel cover 2 for fuel changing. Various elements of the different systems are described in detail.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2316066A DE2316066C2 (en) | 1973-03-30 | 1973-03-30 | Nuclear reactor, especially pressurized water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1448071A true GB1448071A (en) | 1976-09-02 |
Family
ID=5876557
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB869974A Expired GB1448071A (en) | 1973-03-30 | 1974-02-26 | Nuclear reactor installations |
Country Status (4)
Country | Link |
---|---|
JP (1) | JPS5729677B2 (en) |
BE (1) | BE812699A (en) |
DE (1) | DE2316066C2 (en) |
GB (1) | GB1448071A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103871506A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | High-pressure safe injection system for nuclear power station |
CN110010255A (en) * | 2019-04-08 | 2019-07-12 | 南华大学 | A kind of Lead cooled fast breeder reactor residual heat removal system and discharge method |
CN111290443A (en) * | 2020-04-02 | 2020-06-16 | 广西防城港核电有限公司 | Continuous spraying flow control system of nuclear power station voltage stabilizer |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2505532C2 (en) * | 1975-02-10 | 1985-05-23 | Nucledyne Engineering Corp., Reed City, Mich. | Nuclear reactor power plant with coolant supply in the event of an accident-related loss of reactor coolant |
JPS55122193A (en) * | 1979-03-14 | 1980-09-19 | Hitachi Ltd | Device for injecting emergency core cooling water |
US4587080A (en) * | 1982-02-05 | 1986-05-06 | Westinghouse Electric Corp. | Compartmentalized safety coolant injection system |
US4654190A (en) * | 1984-04-05 | 1987-03-31 | Westinghouse Electric Corp. | Emergency feedwater system for steam generators of a nuclear power plant |
US8873695B2 (en) * | 2011-01-06 | 2014-10-28 | Ge-Hitachi Nuclear Energy Americas Llc | Reactor pressure vessel head vents and methods of using the same |
GB2568692B (en) * | 2017-11-23 | 2020-01-22 | Rolls Royce Plc | Nuclear power plants |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE795482A (en) * | 1972-02-19 | 1973-05-29 | Siemens Ag | NUCLEAR REACTOR COOLING SYSTEM |
-
1973
- 1973-03-30 DE DE2316066A patent/DE2316066C2/en not_active Expired
-
1974
- 1974-02-26 GB GB869974A patent/GB1448071A/en not_active Expired
- 1974-03-22 BE BE142339A patent/BE812699A/en unknown
- 1974-03-29 JP JP3547174A patent/JPS5729677B2/ja not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103871506A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | High-pressure safe injection system for nuclear power station |
CN110010255A (en) * | 2019-04-08 | 2019-07-12 | 南华大学 | A kind of Lead cooled fast breeder reactor residual heat removal system and discharge method |
CN110010255B (en) * | 2019-04-08 | 2023-12-15 | 南华大学 | Lead-cooled fast reactor waste heat discharging system and discharging method |
CN111290443A (en) * | 2020-04-02 | 2020-06-16 | 广西防城港核电有限公司 | Continuous spraying flow control system of nuclear power station voltage stabilizer |
CN111290443B (en) * | 2020-04-02 | 2023-04-07 | 广西防城港核电有限公司 | Continuous spraying flow control system of nuclear power station voltage stabilizer |
Also Published As
Publication number | Publication date |
---|---|
BE812699A (en) | 1974-07-15 |
DE2316066C2 (en) | 1982-05-27 |
DE2316066A1 (en) | 1974-10-10 |
JPS5052496A (en) | 1975-05-09 |
JPS5729677B2 (en) | 1982-06-24 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |