BE905205A - Procede et dispositif d'adaptation d'equipements internes superieurs neufs sur la cuve d'un reacteur nucleaire a eau sous pression. - Google Patents

Procede et dispositif d'adaptation d'equipements internes superieurs neufs sur la cuve d'un reacteur nucleaire a eau sous pression.

Info

Publication number
BE905205A
BE905205A BE0/217000A BE217000A BE905205A BE 905205 A BE905205 A BE 905205A BE 0/217000 A BE0/217000 A BE 0/217000A BE 217000 A BE217000 A BE 217000A BE 905205 A BE905205 A BE 905205A
Authority
BE
Belgium
Prior art keywords
tank
internal equipment
pressure water
nuclear reactor
water nuclear
Prior art date
Application number
BE0/217000A
Other languages
English (en)
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
Publication of BE905205A publication Critical patent/BE905205A/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/02—Details of handling arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

La cuve (1) du réacteur étant ouverte et remplie d'eau et les assemblages du coeur enlevés, on monte sur les équipements internes supérieurs (13) des moyens de mesure d'alignement (50) et des moyens de mesure de jeux (56, 58, 59). On introduit les équipements supérieurs (13) dans la cuve et on les dépose sur les équipements inférieurs (8). On réalise les mesures d'alignement. On mesure les jeux de la plaque supérieure de coeur. On mesure les jeux autour des broches de centrage et d'alignement et on usine des pièces d'adaptation qui sont ensuite fixées sur les équipements internes supérieurs (13).
BE0/217000A 1985-08-02 1986-08-01 Procede et dispositif d'adaptation d'equipements internes superieurs neufs sur la cuve d'un reacteur nucleaire a eau sous pression. BE905205A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR8511902A FR2585870B1 (fr) 1985-08-02 1985-08-02 Procede et dispositif d'adaptation d'equipements internes superieurs neufs sur la cuve d'un reacteur nucleaire a eau sous pression.

Publications (1)

Publication Number Publication Date
BE905205A true BE905205A (fr) 1987-02-02

Family

ID=9321946

Family Applications (1)

Application Number Title Priority Date Filing Date
BE0/217000A BE905205A (fr) 1985-08-02 1986-08-01 Procede et dispositif d'adaptation d'equipements internes superieurs neufs sur la cuve d'un reacteur nucleaire a eau sous pression.

Country Status (6)

Country Link
US (1) US4696786A (fr)
KR (1) KR870002604A (fr)
BE (1) BE905205A (fr)
DE (1) DE3626207A1 (fr)
FR (1) FR2585870B1 (fr)
ZA (1) ZA865530B (fr)

Families Citing this family (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4778645A (en) * 1985-12-09 1988-10-18 Westinghouse Electric Corp. Pressurized water reactor having disconnectable two-piece drive rod assemblies, and related methods of assembly and maintenance operations
US4707325A (en) * 1986-07-03 1987-11-17 Westinghouse Electric Corp. Gauge plate for use in customizing a replacement upper core plate in a nuclear reactor, and method of using the gauge plate
DE58907596D1 (de) * 1988-08-03 1994-06-09 Siemens Ag Vorrichtung zum Transportieren und Wenden von Kerngerüstteilen eines Kernreaktors.
FR2635906B1 (fr) * 1988-08-25 1990-11-23 Framatome Sa Dispositif d'instrumentation du coeur d'un reacteur nucleaire a eau sous pression et procede et dispositif d'extraction et de mise en place de ce dispositif d'instrumentation
US4954311A (en) * 1989-01-10 1990-09-04 General Electric Company Control rod housing alignment
US5040287A (en) * 1989-06-19 1991-08-20 The United States Of America As Represented By The United States Department Of Energy Heating equipment installation 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
FR2717608B1 (fr) * 1994-03-15 1996-06-14 Framatome Sa Cuve d'un réacteur nucléaire comportant des moyens de maintien de ses équipements internes inférieurs et procédé d'ajustage des moyens de maintien.
DE4445171C2 (de) * 1994-12-16 2002-05-29 Bbc Reaktor Gmbh Verfahren zum Zerlegen sperriger Teile von Druckbehälter-Einbauten einer kerntechnischen Anlage und zum Aufnehmen der zerlegten Teile
US5864594A (en) * 1995-04-18 1999-01-26 Westinghouse Electric Corporation Apparatus and method for replacing internal components in a nuclear reactor
DE19654155C2 (de) * 1995-12-27 2002-06-27 Toshiba Kawasaki Kk Handhabungsvorrichtung für reaktorinterne Einrichtungen
DE19610102C1 (de) * 1996-03-15 1997-07-10 Siemens Ag Verfahren zum Entsorgen einer in einem Reaktordruckbehälter einer Kernreaktoranlage angeordneten Komponente
JP5537225B2 (ja) * 2010-03-31 2014-07-02 日立Ｇｅニュークリア・エナジー株式会社 改良型制御棒駆動機構取扱装置及びその装置の取扱い方法
FR2966278B1 (fr) * 2010-10-14 2012-12-21 Areva Np Dispositif de support momentane des equipements internes superieurs sur une cuve d'un reacteur nucleaire a eau sous pression
JP6777523B2 (ja) * 2016-12-16 2020-10-28 三菱重工業株式会社 搬送支援装置及び搬送支援方法
US11355252B2 (en) 2016-12-30 2022-06-07 Nuscale Power, Llc Control rod drive mechanism with heat pipe cooling
KR102495798B1 (ko) 2016-12-30 2023-02-03 뉴스케일 파워, 엘엘씨 원격 연결 해제 메커니즘을 가진 제어봉 드라이브 메커니즘(crdm)
US11024433B2 (en) 2016-12-30 2021-06-01 Nuscale Power, Llc Control rod damping system
CN107093481B (zh) * 2017-06-01 2019-03-01 中国核工业第五建设有限公司 制作ap1000核电站中堆内构件用定位镶块的方法

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1337090A (en) * 1970-07-08 1973-11-14 Westinghouse Electric Corp Method of refluelling reactor
FR2262852A1 (en) * 1974-03-01 1975-09-26 Commissariat Energie Atomique Frame lifts reactor control rods during fuel change - fixed frame and moving platform with quick releases speed-up fuel change
US4100021A (en) * 1976-10-18 1978-07-11 Westinghouse Electric Corp. Nuclear reactor vessel and internals alignment apparatus
US4197652A (en) * 1978-04-27 1980-04-15 General Electric Company Plane of reference device

Also Published As

Publication number Publication date
ZA865530B (en) 1987-02-25
FR2585870B1 (fr) 1987-12-31
KR870002604A (ko) 1987-03-31
FR2585870A1 (fr) 1987-02-06
DE3626207A1 (de) 1987-02-12
US4696786A (en) 1987-09-29

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Legal Events

Date Code Title Description
RE Patent lapsed

Owner name: FRAMATOME S.A.

Effective date: 19950831