ES548637A0 - Un metodo de funcionamiento de un sistema de generacion de energia electrica - Google Patents
Un metodo de funcionamiento de un sistema de generacion de energia electricaInfo
- Publication number
- ES548637A0 ES548637A0 ES548637A ES548637A ES548637A0 ES 548637 A0 ES548637 A0 ES 548637A0 ES 548637 A ES548637 A ES 548637A ES 548637 A ES548637 A ES 548637A ES 548637 A0 ES548637 A0 ES 548637A0
- Authority
- ES
- Spain
- Prior art keywords
- electric power
- power generation
- generation system
- electric
- power
- 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.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- 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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/36—Control circuits
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US67079484A | 1984-11-13 | 1984-11-13 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| ES548637A0 true ES548637A0 (es) | 1988-02-16 |
| ES8801873A1 ES8801873A1 (es) | 1988-02-16 |
Family
ID=24691905
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES548637A Expired ES8801873A1 (es) | 1984-11-13 | 1985-11-07 | Un metodo de funcionamiento de un sistema de generacion de energia electrica |
Country Status (5)
| Country | Link |
|---|---|
| EP (1) | EP0185455A1 (es) |
| JP (1) | JPS61118692A (es) |
| KR (1) | KR930011109B1 (es) |
| CN (1) | CN85108160A (es) |
| ES (1) | ES8801873A1 (es) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2619950B1 (fr) * | 1987-08-24 | 1991-11-29 | Framatome Sa | Procede de protection d'un reacteur nucleaire a eau pressurisee contre les defaillances du dispositif d'arret d'urgence |
| DE60209474T2 (de) | 2001-03-29 | 2006-10-12 | Pebble Bed Modular Reactor (Proprietary) Ltd. | Verfahren und vorrichtung zur regelung der temperatur des auslasses eines kernreaktors |
| JP4585527B2 (ja) * | 2006-03-02 | 2010-11-24 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 原子炉システムのトリップ制御方法及び原子炉システム |
| AU2009303608B2 (en) * | 2008-10-13 | 2013-11-14 | Shell Internationale Research Maatschappij B.V. | Using self-regulating nuclear reactors in treating a subsurface formation |
| CN102881340B (zh) * | 2012-09-27 | 2015-09-23 | 中国核电工程有限公司 | 一种能动与非能动相结合的应急停堆系统及方法 |
| CN103985421B (zh) * | 2014-05-06 | 2016-09-28 | 中广核研究院有限公司 | 反应堆未能紧急停堆时提高核电机组安全性的方法 |
| JP6505889B1 (ja) * | 2018-02-28 | 2019-04-24 | 三菱重工業株式会社 | 原子炉の異常緩和設備及び制御棒の固着判定方法 |
| CN109441561B (zh) * | 2018-12-17 | 2021-06-15 | 广西电网有限责任公司电力科学研究院 | 一种核电机组压水堆超温保护系统的保护方法 |
| KR102649452B1 (ko) * | 2022-04-05 | 2024-03-19 | 한국수력원자력 주식회사 | 원자력 발전소에서 원자로냉각재계통 과압사고에 대응하는 방법 및 이를 위한 시스템 |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH432029A (fr) * | 1964-03-27 | 1967-03-15 | Commissariat Energie Atomique | Dispositif de détection du débit d'un liquide |
| JPS5182890A (es) * | 1975-01-17 | 1976-07-20 | Hitachi Ltd | |
| US4075059A (en) * | 1976-04-28 | 1978-02-21 | Combustion Engineering, Inc. | Reactor power reduction system and method |
| US4290851A (en) * | 1979-01-29 | 1981-09-22 | The Babcock & Wilcox Company | Nuclear reactor safety system |
| US4427620A (en) * | 1981-02-04 | 1984-01-24 | Westinghouse Electric Corp. | Nuclear reactor power supply |
-
1985
- 1985-11-06 JP JP60247299A patent/JPS61118692A/ja active Pending
- 1985-11-07 ES ES548637A patent/ES8801873A1/es not_active Expired
- 1985-11-08 CN CN198585108160A patent/CN85108160A/zh active Pending
- 1985-11-13 KR KR1019850008482A patent/KR930011109B1/ko not_active Expired - Lifetime
- 1985-11-13 EP EP85308232A patent/EP0185455A1/en not_active Ceased
Also Published As
| Publication number | Publication date |
|---|---|
| ES8801873A1 (es) | 1988-02-16 |
| EP0185455A1 (en) | 1986-06-25 |
| KR930011109B1 (ko) | 1993-11-24 |
| KR860004423A (ko) | 1986-06-23 |
| JPS61118692A (ja) | 1986-06-05 |
| CN85108160A (zh) | 1986-07-16 |
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