FR3079960B1 - Reacteur nucleaire et procede de maintenance correspondant - Google Patents

Reacteur nucleaire et procede de maintenance correspondant Download PDF

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Publication number
FR3079960B1
FR3079960B1 FR1852975A FR1852975A FR3079960B1 FR 3079960 B1 FR3079960 B1 FR 3079960B1 FR 1852975 A FR1852975 A FR 1852975A FR 1852975 A FR1852975 A FR 1852975A FR 3079960 B1 FR3079960 B1 FR 3079960B1
Authority
FR
France
Prior art keywords
cuff
nuclear reactor
adapter
axial end
maintenance method
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
FR1852975A
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English (en)
Other versions
FR3079960A1 (fr
Inventor
Christian Brenin
Denis Pollier
Laurent Cahouet
Denis CEDAT
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
Priority to FR1852975A priority Critical patent/FR3079960B1/fr
Application filed by Framatome SA filed Critical Framatome SA
Priority to PCT/EP2019/058487 priority patent/WO2019193088A1/fr
Priority to KR1020207030102A priority patent/KR102649496B1/ko
Priority to EP19714223.5A priority patent/EP3776595A1/fr
Priority to US17/045,086 priority patent/US11557402B2/en
Priority to JP2020554179A priority patent/JP7317041B2/ja
Priority to CN201980023011.2A priority patent/CN111919265A/zh
Priority to TW108112204A priority patent/TW201944432A/zh
Publication of FR3079960A1 publication Critical patent/FR3079960A1/fr
Application granted granted Critical
Publication of FR3079960B1 publication Critical patent/FR3079960B1/fr
Priority to ZA2020/05771A priority patent/ZA202005771B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/032Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • G21C13/036Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/12Means for moving control elements to desired position
    • G21C7/16Hydraulic or pneumatic drive
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

Le réacteur nucléaire comprend : - des tubes guides (12) ; - des traversées de couvercle (22), comprenant chacune un adaptateur tubulaire (24) fixé dans un des orifices (2a) et délimitant un passage interne (34), chaque traversée de couvercle (22) comprenant en outre une manchette tubulaire (36) engagée dans le passage interne (34) et s'étendant axialement dans le prolongement d'un des tubes guides (12); chaque manchette (36) étant suspendue par une extrémité axiale supérieure de manchette (38) reposant sur une portée supérieure (40) ménagée sur l'adaptateur (24) correspondant ; une extrémité axiale inférieure (48) de la manchette (36) faisant saillie axialement dans la cuve (1) au-delà de l'adaptateur (24) et étant séparée d'une extrémité axiale supérieure (54) du tube guide (12) correspondant par un interstice axial de hauteur axiale inférieure à 50 millimètres.
FR1852975A 2018-04-05 2018-04-05 Reacteur nucleaire et procede de maintenance correspondant Active FR3079960B1 (fr)

Priority Applications (9)

Application Number Priority Date Filing Date Title
FR1852975A FR3079960B1 (fr) 2018-04-05 2018-04-05 Reacteur nucleaire et procede de maintenance correspondant
KR1020207030102A KR102649496B1 (ko) 2018-04-05 2019-04-04 원자로 및 대응하는 유지보수 방법
EP19714223.5A EP3776595A1 (fr) 2018-04-05 2019-04-04 Réacteur nucléaire et procédé de maintenance correspondant
US17/045,086 US11557402B2 (en) 2018-04-05 2019-04-04 Nuclear reactor, guide tube support, and corresponding maintenance method
PCT/EP2019/058487 WO2019193088A1 (fr) 2018-04-05 2019-04-04 Réacteur nucléaire et procédé de maintenance correspondant
JP2020554179A JP7317041B2 (ja) 2018-04-05 2019-04-04 原子炉およびそれに対応した保守方法
CN201980023011.2A CN111919265A (zh) 2018-04-05 2019-04-04 核反应堆以及对应的维护方法
TW108112204A TW201944432A (zh) 2018-04-05 2019-04-08 核反應爐以及相應的維護方法
ZA2020/05771A ZA202005771B (en) 2018-04-05 2020-09-17 Nuclear reactor and corresponding maintenance method

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR1852975 2018-04-05
FR1852975A FR3079960B1 (fr) 2018-04-05 2018-04-05 Reacteur nucleaire et procede de maintenance correspondant

Publications (2)

Publication Number Publication Date
FR3079960A1 FR3079960A1 (fr) 2019-10-11
FR3079960B1 true FR3079960B1 (fr) 2020-03-13

Family

ID=62948224

Family Applications (1)

Application Number Title Priority Date Filing Date
FR1852975A Active FR3079960B1 (fr) 2018-04-05 2018-04-05 Reacteur nucleaire et procede de maintenance correspondant

Country Status (9)

Country Link
US (1) US11557402B2 (fr)
EP (1) EP3776595A1 (fr)
JP (1) JP7317041B2 (fr)
KR (1) KR102649496B1 (fr)
CN (1) CN111919265A (fr)
FR (1) FR3079960B1 (fr)
TW (1) TW201944432A (fr)
WO (1) WO2019193088A1 (fr)
ZA (1) ZA202005771B (fr)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20220139580A1 (en) * 2019-02-25 2022-05-05 Westinghouse Electric Company Llc Anti-rotation arrangement for thermal sleeves
CN114365235A (zh) * 2019-02-25 2022-04-15 西屋电气有限责任公司 用于热套管的防旋转布置

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2488033A1 (fr) * 1980-07-31 1982-02-05 Framatome Sa Dispositif de protection des mecanismes de commande des grappes de controle pendant les essais d'un reacteur nucleaire
US4654185A (en) * 1984-12-05 1987-03-31 Westinghouse Electric Corp. Deep beam reactor vessel head and nuclear reactor including same
US4714584A (en) * 1985-02-12 1987-12-22 Westinghouse Electric Corporation Flow limiting head adapter extension
FR2595501B1 (fr) * 1986-03-07 1988-06-10 Framatome Sa Equipements internes de reacteurs nucleaires a cuve allongee
FR2600812B1 (fr) * 1986-06-27 1990-06-01 Framatome Sa Dispositif d'entrainement de barre de commande de reacteur nucleaire, a clapet mobile
FR2620557B1 (fr) * 1987-09-11 1990-01-12 Framatome Sa Assemblage combustible nucleaire a fractionnement de debit
US5053189A (en) * 1989-10-16 1991-10-01 Westinghouse Electric Corp. System providing improved guidance support with restricted coolant flow for control rods in the upper head plenum of a nuclear reactor
FR2667194B1 (fr) * 1990-09-20 1993-08-06 Framatome Sa Dispositif de guidage de grappe de controle de reacteur nucleaire.
FR2689297B1 (fr) * 1992-03-25 1994-07-01 Framatome Sa Procede de demontage et de remplacement d'une manchette thermique d'une traversee d'un couvercle de cuve d'un reacteur nucleaire a eau sous pression et manchette thermique demontable de remplacement.
FR2693310B1 (fr) * 1992-07-03 1994-10-14 Framatome Sa Procédé d'utilisation d'un doigt de gant d'un réacteur nucléaire à eau sous pression et dispositif de réglage de la position axiale du doigt de gant.
DE4236005C2 (de) * 1992-10-24 1994-08-25 Bbc Reaktor Gmbh Verfahren zum Austausch eines einen Deckel eines Kernreaktordruckbehälters durchsetzenden Stutzens
FR2727560B1 (fr) * 1994-11-24 1997-01-03 Framatome Sa Piece tubulaire de traversee du couvercle de la cuve d'un reacteur nucleaire a manchette thermique amelioree
FR2813700B1 (fr) * 2000-09-06 2002-12-06 Framatome Sa Procede de reparation d'un adaptateur de traversee du couvercle d'une cuve de reacteur nucleaire
FR2859308B1 (fr) * 2004-02-10 2006-01-06 Jeumont Sa Dispositif de deplacement d'une barre de commande d'un reacteur nucleaire a eau sous pression et procede de montage du dispositif sur un couvercle de cuve
US7995701B2 (en) * 2008-05-21 2011-08-09 Westinghouse Electric Company Llc Nuclear core component hold-down assembly
US9659674B2 (en) * 2012-04-27 2017-05-23 Westinghouse Electric Company Llc Instrumentation and control penetration flange for pressurized water reactor

Also Published As

Publication number Publication date
ZA202005771B (en) 2021-08-25
JP7317041B2 (ja) 2023-07-28
KR20200141458A (ko) 2020-12-18
EP3776595A1 (fr) 2021-02-17
TW201944432A (zh) 2019-11-16
US11557402B2 (en) 2023-01-17
FR3079960A1 (fr) 2019-10-11
US20210366624A1 (en) 2021-11-25
JP2021520491A (ja) 2021-08-19
CN111919265A (zh) 2020-11-10
KR102649496B1 (ko) 2024-03-19
WO2019193088A1 (fr) 2019-10-10

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