FR3100920B1 - Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire - Google Patents

Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire Download PDF

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Publication number
FR3100920B1
FR3100920B1 FR1910211A FR1910211A FR3100920B1 FR 3100920 B1 FR3100920 B1 FR 3100920B1 FR 1910211 A FR1910211 A FR 1910211A FR 1910211 A FR1910211 A FR 1910211A FR 3100920 B1 FR3100920 B1 FR 3100920B1
Authority
FR
France
Prior art keywords
steam generator
nuclear reactor
centrifugal separator
repair kit
elements
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.)
Active
Application number
FR1910211A
Other languages
English (en)
Other versions
FR3100920A1 (fr
Inventor
François Libault
Denis Heurgue
François Janin
Jean-Claude Simonato
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
Priority to FR1910211A priority Critical patent/FR3100920B1/fr
Priority to CN202080064901.0A priority patent/CN114423993A/zh
Priority to PCT/EP2020/075863 priority patent/WO2021053015A1/fr
Publication of FR3100920A1 publication Critical patent/FR3100920A1/fr
Application granted granted Critical
Publication of FR3100920B1 publication Critical patent/FR3100920B1/fr
Active legal-status Critical Current
Anticipated expiration legal-status Critical

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Classifications

    • 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
    • F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
    • F22B1/12—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam produced by an indirect cyclic process
    • F22B1/123—Steam generators downstream of a nuclear boiling water reactor
    • 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 far as they are not classified, according to a specified heating fluid, in another group
    • F22B1/025—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 far as they are not classified, according to a specified heating fluid, in another group with vertical U shaped tubes carried on a horizontal tube sheet
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • F22B37/003—Maintenance, repairing or inspecting equipment positioned in or via the headers
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • F22B37/007—Installation or removal of nuclear steam generators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/26—Steam-separating arrangements
    • F22B37/32—Steam-separating arrangements using centrifugal force
    • F22B37/327—Steam-separating arrangements using centrifugal force specially adapted for steam generators of nuclear power plants
    • 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
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Plasma & Fusion (AREA)
  • Cyclones (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Centrifugal Separators (AREA)

Abstract

Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire La méthode comprend les étapes suivantes : - Approvisionnement d’un ensemble (E) d’éléments de séparateur centrifuge ; - Introduction desdits éléments dans le générateur de vapeur (1) à travers le trou d’homme (30) ; - Assemblage desdits éléments de séparateur centrifuge les uns aux autres à l’intérieur du générateur de vapeur (1), lesdits éléments de séparateur centrifuge formant après assemblage un tronçon tubulaire supérieur (39) de remplacement et des pales (41) de remplacement pour un séparateur centrifuge. Figure pour l'abrégé : figure 4
FR1910211A 2019-09-16 2019-09-16 Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire Active FR3100920B1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
FR1910211A FR3100920B1 (fr) 2019-09-16 2019-09-16 Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire
CN202080064901.0A CN114423993A (zh) 2019-09-16 2020-09-16 用于修理核反应堆的蒸汽发生器的修理方法和组件
PCT/EP2020/075863 WO2021053015A1 (fr) 2019-09-16 2020-09-16 Méthode et ensemble de réparation d'un générateur de vapeur d'un réacteur nucléaire

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR1910211 2019-09-16
FR1910211A FR3100920B1 (fr) 2019-09-16 2019-09-16 Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire

Publications (2)

Publication Number Publication Date
FR3100920A1 FR3100920A1 (fr) 2021-03-19
FR3100920B1 true FR3100920B1 (fr) 2021-10-01

Family

ID=69572044

Family Applications (1)

Application Number Title Priority Date Filing Date
FR1910211A Active FR3100920B1 (fr) 2019-09-16 2019-09-16 Méthode et ensemble de réparation d’un générateur de vapeur d’un réacteur nucléaire

Country Status (3)

Country Link
CN (1) CN114423993A (fr)
FR (1) FR3100920B1 (fr)
WO (1) WO2021053015A1 (fr)

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2654351A (en) * 1949-02-01 1953-10-06 Babcock & Wilcox Co Fluid separator
FR2480905A1 (fr) * 1980-04-18 1981-10-23 Framatome Sa Dispositif de separation d'eau et de vapeur a la sortie d'enceinte de vaporisation d'un generateur de vapeur
FR2707733B1 (fr) * 1993-07-12 1995-09-01 Framatome Sa Générateur de vapeur à cyclones démontables.
JP2010043969A (ja) * 2008-08-13 2010-02-25 Hitachi-Ge Nuclear Energy Ltd 気水分離器及びこれを備えた沸騰水型原子炉
US10847273B2 (en) * 2014-01-17 2020-11-24 Ge-Hitachi Nuclear Energy Americas Llc Steam separator and nuclear boiling water reactor including the same
KR102013074B1 (ko) * 2018-10-19 2019-08-21 한전케이피에스 주식회사 원자력발전소 증기발생기의 습분분리기 조립체 및 습분분리기의 교체방법

Also Published As

Publication number Publication date
WO2021053015A1 (fr) 2021-03-25
FR3100920A1 (fr) 2021-03-19
CN114423993A (zh) 2022-04-29

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