ES2030809T3 - Procedimiento de proteccion de un reactor nuclear de agua presurizada contra los fallos de su dispositivo de parada de urgencia. - Google Patents

Procedimiento de proteccion de un reactor nuclear de agua presurizada contra los fallos de su dispositivo de parada de urgencia.

Info

Publication number
ES2030809T3
ES2030809T3 ES198888113061T ES88113061T ES2030809T3 ES 2030809 T3 ES2030809 T3 ES 2030809T3 ES 198888113061 T ES198888113061 T ES 198888113061T ES 88113061 T ES88113061 T ES 88113061T ES 2030809 T3 ES2030809 T3 ES 2030809T3
Authority
ES
Spain
Prior art keywords
emergency stop
failures
nuclear power
nuclear reactor
stop device
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 - Lifetime
Application number
ES198888113061T
Other languages
English (en)
Inventor
Olivier Onfroy
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.)
Areva NP SAS
Original Assignee
Framatome SA
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
Family has litigation
First worldwide family litigation filed litigation Critical https://patents.darts-ip.com/?family=9354377&utm_source=***_patent&utm_medium=platform_link&utm_campaign=public_patent_search&patent=ES2030809(T3) "Global patent litigation dataset” by Darts-ip is licensed under a Creative Commons Attribution 4.0 International License.
Application filed by Framatome SA filed Critical Framatome SA
Application granted granted Critical
Publication of ES2030809T3 publication Critical patent/ES2030809T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Safety Devices In Control Systems (AREA)
  • Control Of Turbines (AREA)

Abstract

EN EL CASO DE UN INCIDENTE EN EL CIRCUITO DE ENFRIAMIENTO SECUNDARIO (12, 19, 13, 15, 16, 2) DE UNA CENTRAL NUCLEAR QUE IMPIDE EL ENFRIAMIENTO DEL AGUA DEL CIRCUITO PRIMARIO (1, 2, 3, 4, 5) EN LOS GENERADORES DE VAPOR (2) COMUNES A ESTOS DOS CIRCUITOS, UNA ORDEN DE PARADA DE EMERGENCIA ES DADA PARA HACER CAER LAS PALANCAS DE CONTROL Y DE PARADA (1A) EN EL NUCLEO (1C) DEL REACTOR. SEGUN EL PRESENTE INVENTO, SI ESTA ORDEN NO ES EJECUTADA, LA SUBSISTENCIA DE UNA POTENCIA NUCLEAR IMPORTANTE COMANDA LA PARADA DE LAS BOMBAS PRIMARIAS (3). UNA ELEVACION RAPIDA DE LA TEMPERATURA DEL AGUA EN EL NUCLEO PARA EVITAR QUE UNA SOBREPRESION ULTERIOR DETERIORE EL CIRCUITO PRIMARIO. EL INVENTO SE APLICA ESPECIALMENTE EN CENTRALES NUCLEARES ELECTROGENAS.
ES198888113061T 1987-08-24 1988-08-11 Procedimiento de proteccion de un reactor nuclear de agua presurizada contra los fallos de su dispositivo de parada de urgencia. Expired - Lifetime ES2030809T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR8711848A FR2619950B1 (fr) 1987-08-24 1987-08-24 Procede de protection d'un reacteur nucleaire a eau pressurisee contre les defaillances du dispositif d'arret d'urgence

Publications (1)

Publication Number Publication Date
ES2030809T3 true ES2030809T3 (es) 1992-11-16

Family

ID=9354377

Family Applications (1)

Application Number Title Priority Date Filing Date
ES198888113061T Expired - Lifetime ES2030809T3 (es) 1987-08-24 1988-08-11 Procedimiento de proteccion de un reactor nuclear de agua presurizada contra los fallos de su dispositivo de parada de urgencia.

Country Status (9)

Country Link
US (1) US4948551A (es)
EP (1) EP0306725B1 (es)
JP (1) JPS6469996A (es)
KR (1) KR890004341A (es)
CN (1) CN1018214B (es)
DE (1) DE3871042D1 (es)
ES (1) ES2030809T3 (es)
FR (1) FR2619950B1 (es)
ZA (1) ZA886297B (es)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2000350414A (ja) * 1999-06-03 2000-12-15 Hitachi Ltd タービン発電機の運転方法
US6781331B2 (en) * 2002-09-13 2004-08-24 General Electric Company Method and apparatus for regulating motor generator output
DE102011111246B4 (de) * 2011-08-22 2016-07-14 Westinghouse Electric Germany Gmbh System und Verfahren zur beschleunigten Einspeisung eines die Reaktivität beeinflussenden Mediums in einen schwerwassermoderierten Reaktor
CN104332206B (zh) * 2013-07-22 2017-02-08 中国核动力研究设计院 一种压水堆核电站启/停堆工况的超压保护方法
CN104332188A (zh) * 2013-07-22 2015-02-04 中国核动力研究设计院 一种丧失正常给水-atws事故下缓解一回路超压的方法
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
CN106340333B (zh) * 2016-09-05 2018-05-01 中广核工程有限公司 核电站安全动作执行情况监测方法和***
JP6828195B2 (ja) * 2017-12-29 2021-02-10 ジョイント ストック カンパニー アトムエネルゴプロエクトＪｏｉｎｔ Ｓｔｏｃｋ Ｃｏｍｐａｎｙ Ａｔｏｍｅｎｅｒｇｏｐｒｏｅｋｔ パージ運転およびドレネージとの二重回路原子炉の蒸気発生装置
CN109256223B (zh) * 2018-11-13 2019-12-10 中国核动力研究设计院 一种余热排出***和方法
CN110136852B (zh) * 2019-04-30 2020-08-07 中广核核电运营有限公司 一种核电站一回路水压试验超压保护***
CN111128414B (zh) * 2019-12-31 2022-07-26 中国核动力研究设计院 一种核电厂能动与非能动相结合的安全***及其方法
CN111554425B (zh) * 2020-05-15 2022-02-11 中国核动力研究设计院 一种压水堆核电厂极小破口失水事故应对方法

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2920025A (en) * 1956-10-26 1960-01-05 John B Anderson Neutronic reactors
US3929513A (en) * 1968-07-25 1975-12-30 Gould Inc Lead alloy products
US4075059A (en) * 1976-04-28 1978-02-21 Combustion Engineering, Inc. Reactor power reduction system and method
US4222822A (en) * 1977-01-19 1980-09-16 Westinghouse Electric Corp. Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution
JPS5445482A (en) * 1977-09-16 1979-04-10 Hitachi Ltd Boiling water type reactor
JPS61118692A (ja) * 1984-11-13 1986-06-05 ウエスチングハウス　エレクトリック　コ−ポレ−ション 加圧水型原子炉発電システムの運転方法
FR2610446B1 (fr) * 1987-01-30 1991-11-29 Framatome Sa Procede de determination du seuil d'alarme du rapport d'echauffement critique, dispositif de mise en oeuvre, et procede de pilotage d'un reacteur nucleaire

Also Published As

Publication number Publication date
FR2619950B1 (fr) 1991-11-29
DE3871042D1 (de) 1992-06-17
US4948551A (en) 1990-08-14
KR890004341A (ko) 1989-04-21
EP0306725A1 (fr) 1989-03-15
FR2619950A1 (fr) 1989-03-03
CN1018214B (zh) 1992-09-09
ZA886297B (en) 1989-05-30
JPS6469996A (en) 1989-03-15
EP0306725B1 (fr) 1992-05-13
CN1032259A (zh) 1989-04-05

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