ES8801873A1 - 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
- ES8801873A1 ES8801873A1 ES548637A ES548637A ES8801873A1 ES 8801873 A1 ES8801873 A1 ES 8801873A1 ES 548637 A ES548637 A ES 548637A ES 548637 A ES548637 A ES 548637A ES 8801873 A1 ES8801873 A1 ES 8801873A1
- Authority
- ES
- Spain
- Prior art keywords
- loss
- pwr
- feedwater
- event
- controlling
- 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
- 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)
Abstract
METODO PARA EL FUNCIONAMIENTO DE UN SISTEMA DE GENERACION DE ENERGIA ELECTRICA POR REACTOR DE AGUA PRESURIZADA, EN EL CASO DE FALLO DE SU SISTEMA PRINCIPAL DE AGUA DE ALIMENTACION. CONSISTE EN ACCIONAR SELECTIVAMENTE EL REACTOR DE UN MODO MANUAL, DE MANERA QUE LAS VARILLAS DE CONTROL DEL REACTOR SEAN INTRODUCIDAS Y EXTRAIDAS DE DICHO REACTOR MANUALMENTE Y EN FUNCION DE LA TEMPERATURA Y CARGA DEL REACTOR. UNA SEÑAL DE ACTIVACION ES GENERADA EN RESPUESTA A UNA VELOCIDAD DE CIRCULACION ANORMAL BAJA, PREDETERMINADA POR DEBAJO DE UN VALOR PRESELECCIONADO EN EL SISTEMA PRINCIPAL DE AGUA DE ALIMENTACION, Y COMO CONSECUENCIA DE ELLO Y DE FORMA AUTOMATICA LAS VARILLAS DE CONTROL SON INTRODUCIDAS ESCALONADAMENTE EN EL REACTOR A LA MAXIMA VELOCIDAD.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US67079484A | 1984-11-13 | 1984-11-13 |
Publications (2)
Publication Number | Publication Date |
---|---|
ES8801873A1 true ES8801873A1 (es) | 1988-02-16 |
ES548637A0 ES548637A0 (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 (8)
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 |
US7139351B2 (en) | 2001-03-29 | 2006-11-21 | Pebble Bed Modular Reactor (Proprietary) Limited | Method of and control system for controlling a nuclear reactor outlet temperature |
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 |
AU2009303604B2 (en) * | 2008-10-13 | 2013-09-26 | Shell Internationale Research Maatschappij B.V. | Circulated heated transfer fluid heating of subsurface hydrocarbon formations |
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 |
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 active IP Right Grant
- 1985-11-13 EP EP85308232A patent/EP0185455A1/en not_active Ceased
Also Published As
Publication number | Publication date |
---|---|
EP0185455A1 (en) | 1986-06-25 |
JPS61118692A (ja) | 1986-06-05 |
ES548637A0 (es) | 1988-02-16 |
KR860004423A (ko) | 1986-06-23 |
CN85108160A (zh) | 1986-07-16 |
KR930011109B1 (ko) | 1993-11-24 |
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