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 electrica

Info

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
Application number
ES548637A
Other languages
English (en)
Other versions
ES548637A0 (es
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Westinghouse Electric Corp
Original Assignee
Westinghouse Electric Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of ES548637A0 publication Critical patent/ES548637A0/es
Publication of ES8801873A1 publication Critical patent/ES8801873A1/es
Expired legal-status Critical Current

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.
ES548637A 1984-11-13 1985-11-07 Un metodo de funcionamiento de un sistema de generacion de energia electrica Expired ES8801873A1 (es)

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 ES548637A0 (es) 1988-02-16
ES8801873A1 true 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)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
ES548637A0 (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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