ES2025792T3 - Procedimiento para la substitucion integral de un generador de vapor de un reactor de agua a presion. - Google Patents

Procedimiento para la substitucion integral de un generador de vapor de un reactor de agua a presion.

Info

Publication number
ES2025792T3
ES2025792T3 ES198888400925T ES88400925T ES2025792T3 ES 2025792 T3 ES2025792 T3 ES 2025792T3 ES 198888400925 T ES198888400925 T ES 198888400925T ES 88400925 T ES88400925 T ES 88400925T ES 2025792 T3 ES2025792 T3 ES 2025792T3
Authority
ES
Spain
Prior art keywords
steam generator
pipes
procedure
generator
substitution
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
ES198888400925T
Other languages
English (en)
Inventor
Alain Martin
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
Application filed by Framatome SA filed Critical Framatome SA
Application granted granted Critical
Publication of ES2025792T3 publication Critical patent/ES2025792T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes for nuclear reactors, as long as they are not classified according to a specified heating fluid, in another group
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S122/00—Liquid heaters and vaporizers
    • Y10S122/11—Removable steam-heating elements
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00—Metal working
    • Y10T29/49—Method of mechanical manufacture
    • Y10T29/49718—Repairing
    • Y10T29/49721—Repairing with disassembling
    • Y10T29/4973—Replacing of defective part

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Sustainable Development (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Jet Pumps And Other Pumps (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Electric Connection Of Electric Components To Printed Circuits (AREA)

Abstract

EL PROCEDIMIENTO CONSISTE EN SEPARAR EL GENERADOR DE VAPOR USADO (1) DEL CIRCUITO PRIMARIO, MEDIANTE CORTE DE LAS CANALIZACIONES (3,5) PROXIMAS A LOS TUBOS DEL GENERADOR DE VAPOR, EXTRAER EL GENERADOR DE VAPOR USADO, COLOCAR UNO NUEVO Y SOLDAR LOS TUBOS DEL GENERADOR NUEVO A LAS CANALIZACIONES PRIMARIAS (3,5). SE EFECTUAN MEDICIONES TOPOMETRICAS SOBRE EL GENERADOR NUEVO, SOBRE EL GENERADOR DE VAPOR USADO (1) SITUADO EN SU ALOJAMIENTO (11) Y EN DICHO ALOJAMIENTO (11) UNA VEZ EXTRAIDO EL GENERADOR USADO (1). LA COMPARACION DE LAS MEDICIONES TOPOMETRICAS PERMITE DETERMINAR EL PROCEDIMIENTO DE SUSTITUCION, ES DECIR EL NUMERO DE CORTES A EFECTUAR EN LAS CANALIZACIONES PRIMARIAS (3,5), LAS MODIFICACIONES EN LOS DISPOSITIVOS DE SOPORTE Y DE POSICIONAMIENTO (8,17) Y LA POSICION DE LOS CHAFLANES DE SOLDEO DE LAS CANALIZACIONES (3,5) Y DE LOS TUBOS DEL GENERADOR DE VAPOR NUEVO.
ES198888400925T 1987-04-27 1988-04-15 Procedimiento para la substitucion integral de un generador de vapor de un reactor de agua a presion. Expired - Lifetime ES2025792T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR8705936A FR2614462B1 (fr) 1987-04-27 1987-04-27 Procede de remplacement integral d'un generateur de vapeur d'un reacteur nucleaire a eau sous pression

Publications (1)

Publication Number Publication Date
ES2025792T3 true ES2025792T3 (es) 1992-04-01

Family

ID=9350520

Family Applications (1)

Application Number Title Priority Date Filing Date
ES198888400925T Expired - Lifetime ES2025792T3 (es) 1987-04-27 1988-04-15 Procedimiento para la substitucion integral de un generador de vapor de un reactor de agua a presion.

Country Status (7)

Country Link
US (1) US4847038A (es)
EP (1) EP0289388B1 (es)
JP (1) JPS63284496A (es)
KR (1) KR880013176A (es)
DE (1) DE3864180D1 (es)
ES (1) ES2025792T3 (es)
FR (1) FR2614462B1 (es)

Families Citing this family (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4994230A (en) * 1989-09-19 1991-02-19 Mk Ferguson Company Template method for replacing a vessel in a pipe system
US5061432A (en) * 1990-03-05 1991-10-29 Westinghouse Electric Corp. Apparatus for facilitating the servicing of inverted canned pump motors having limited access space and restricted access time especially in nuclear power plants
US5307386A (en) * 1992-06-24 1994-04-26 Westinghouse Electric Corp. Apparatus and method for servicing an elongated suspended pump motor in an electric power plant with limited access
FR2719149B1 (fr) * 1994-04-26 1996-07-19 Framatome Sa Procédé de remplacement d'un générateur de vapeur usagé d'un réacteur nucléaire à eau sous pression.
DE4429012C1 (de) * 1994-08-16 1996-02-08 Siemens Ag Verfahren zum Austausch einer im Inneren eines Containments eines Kernreaktors befindlichen Komponente
US6502291B2 (en) * 1998-10-26 2003-01-07 Fritz Stahlecker Process for exchanging the bearings of a traversing fiber guiding rod and textile machine accommodating same
DE19849233A1 (de) * 1998-10-26 2000-04-27 Fritz Stahlecker Verfahren zum Auswechseln von Lagern einer changierenden Fadenführerstange
JP4276808B2 (ja) * 1999-09-29 2009-06-10 日立Ｇｅニュークリア・エナジー株式会社 原子力プラントの機器搬出方法
FR2808614B1 (fr) * 2000-05-04 2002-08-02 Framatome Sa Procede et dispositif de remplacement d'une partie d'un circuit d'un reacteur nucleaire
FR2833876B1 (fr) * 2001-12-20 2004-04-02 Framatome Anp Procede et dispositif de decoupage thermique d'un composant dans un milieu hostile excluant la presence d'operateurs
FR2837612B1 (fr) * 2002-03-22 2004-07-16 Framatome Anp Procede et dispositif de remplacement et procede de reparation d'un troncon d'une canalisation du circuit primaire d'un reacteur nucleaire
JP4114394B2 (ja) * 2002-05-16 2008-07-09 株式会社Ｉｈｉ フランジ位置計測システム
JP4114550B2 (ja) * 2003-06-05 2008-07-09 株式会社Ｉｈｉ プラントの連結管製作方法
FR2874450B1 (fr) * 2004-08-19 2006-11-24 Framatome Anp Sas Procede et dispositif de calage adaptatif des composants d'au moins une boucle d'un circuit primaire d'une centrale nucleaire
KR100811003B1 (ko) * 2005-11-30 2008-03-11 인제대학교 산학협력단 화장실 출입구 시야 차단장치
CN101620892B (zh) * 2009-07-30 2012-02-08 华北电力大学 一种大功率压水堆核电站一回路系统结构设计
FR2953581B1 (fr) * 2009-12-08 2011-12-30 Jspm Support moteur d'un groupe motopompe primaire d'un reacteur nucleaire a eau pressurisee
CN101839467B (zh) * 2010-05-10 2012-05-16 中国核电工程有限公司 一种压水堆核电站蒸汽发生器、主管道和主回路安装方法
CN102169736B (zh) * 2011-01-19 2013-01-23 中国核工业第五建设有限公司 一种核电站冷却剂系统主管道的安装方法
US9666313B2 (en) 2012-04-17 2017-05-30 Bwxt Mpower, Inc. Small modular reactor refueling sequence
US10546662B2 (en) 2013-03-15 2020-01-28 Bwxt Mpower, Inc. Upper vessel transport
US9656841B2 (en) * 2014-10-06 2017-05-23 Phil Madron Fire tube implement, system, and method
KR101613814B1 (ko) * 2015-01-29 2016-04-19 문인득 2루프 가압경수로형 증기 발생기의 교체 방법
KR101675077B1 (ko) * 2015-12-07 2016-11-10 문인득 2루프 가압경수로형 증기발생기의 시공방법 및 이를 위한 원자로 배관 시공용 역변위 시스템
DE102016122513B3 (de) * 2016-11-22 2017-03-16 Areva Gmbh Verfahren zum Demontieren eines Dampferzeugers oder Wärmetauschers, insbesondere eines Dampferzeugers oder Wärmetauschers eines Kernkraftwerks
CN107339932B (zh) * 2016-12-23 2020-11-03 广东核电合营有限公司 连接管整体更换方法
GB201907315D0 (en) * 2019-05-24 2019-07-10 Rolls Royce Plc Containment for a PWR nuclear power plant
CN115169015A (zh) * 2022-05-09 2022-10-11 中广核工程有限公司 蒸汽发生器更换辅助系统、方法、装置、设备和介质

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4230527A (en) * 1977-04-29 1980-10-28 Alexander Cella Steam generator for use in nuclear power plants
US4199857A (en) * 1978-05-01 1980-04-29 Westinghouse Electric Corp. Tube bundle removal method and apparatus
US4345549A (en) * 1979-12-17 1982-08-24 Ansaldo Societa Per Azioni Steam-generator with improved facilities for replacement of parts

Also Published As

Publication number Publication date
FR2614462A1 (fr) 1988-10-28
JPS63284496A (ja) 1988-11-21
US4847038A (en) 1989-07-11
EP0289388B1 (fr) 1991-08-14
EP0289388A1 (fr) 1988-11-02
KR880013176A (ko) 1988-11-30
FR2614462B1 (fr) 1989-07-28
DE3864180D1 (de) 1991-09-19

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