ES2087661T3 - Aparato y procedimiento para el mantenimiento de barras de control. - Google Patents

Aparato y procedimiento para el mantenimiento de barras de control.

Info

Publication number
ES2087661T3
ES2087661T3 ES93306461T ES93306461T ES2087661T3 ES 2087661 T3 ES2087661 T3 ES 2087661T3 ES 93306461 T ES93306461 T ES 93306461T ES 93306461 T ES93306461 T ES 93306461T ES 2087661 T3 ES2087661 T3 ES 2087661T3
Authority
ES
Spain
Prior art keywords
control rod
radioactive
tool
adjustable
roller
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
ES93306461T
Other languages
English (en)
Inventor
James Elwood Cearley
James Robert Punches
John Gedees Erbes
Matthew George Garbett
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Application granted granted Critical
Publication of ES2087661T3 publication Critical patent/ES2087661T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • 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
    • G21C19/02Details of handling arrangements
    • 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
    • G21C19/207Assembling, maintenance or repair of reactor components
    • 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
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10TTECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00Metal working
    • Y10T29/49Method of mechanical manufacture
    • Y10T29/49718Repairing
    • Y10T29/49721Repairing with disassembling
    • Y10T29/4973Replacing of defective part
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10TTECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00Metal working
    • Y10T29/53Means to assemble or disassemble
    • Y10T29/531Nuclear device

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

SE PROPORCIONAN UN APARATO Y METODO PARA PONER EN SERVICIO UNA VARILLA DE MANDO (18) NUCLEAR IRRADIADA BAJO EL AGUA, EN UN ESTANQUE (24) DE SERVICIO DEL EDIFICIO DEL REACTOR. UNA MESA GIRATORIA (68A), CONTENIENDO UNA PLURALIDAD DE HERRAMIENTAS (70) SEPARADAS SE POSICIONA ADYACENTE A LA VARILLA DE CONTROL (18). UNA PRIMERA HERRAMIENTA (70A) ALINEA LA MESA GIRATORIA (68A) RESPECTO AL RODILLO RADIOACTIVO (32) INSTALADO EN LA VARILLA DE CONTROL (18) MEDIANTE UNA ESPIGA RADIOACTIVA (42 A SU TRAVES. LA MESA GIRATORIA (68A) ES GRADUABLE PARA POSICIONAR UNA SEGUNDA HERRAMIENTA (70B) ADYACENTE AL RODILLO RADIOACTIVO (32) Y ESPIGA (42), CON LA SEGUNDA HERRAMIENTA (70B) SIENDO EFECTIVA PARA LIBERAR A LA ESPIGA RADIOACTIVA (42) DE LA VARILLA DE MANDO (18). LA MESA GIRATORIA (68A) ES GRADUABLE PARA POSICIONAR UNA TERCERA HERRAMIENTA (70C) ADYACENTE AL RODILLO RADIOACTIVO (32) Y ESPIGA (42), PARA EXTRAER LA ESPIGA RADIOACTIVA (42) Y EL RODILLO (32) DE LA VARILLA DE MANDO (18). EN POSTERIORES VERSIONES DELA INVENCION, LA MESA GIRATORIA (68A) ES ADEMAS GRADUABLE PARA POSICIONAR UNA CUARTA HERRAMIENTA (70D) ADYACENTE A LA VARILLA DE MANDO (18), PARA MANDRILAR LA APERTURA DE LA ESPIGA (40A, 40B), A CUYO TRAVES SE INSTALO LA ESPIGA RADIOACTIVA (42). LA MESA GRADUABLE (68A) INCLUYE ADEMAS UNA QUINTA HERRAMIENTA (70E) QUE ES GRADUABLE EN POSICION ADYACENTE A LA VARILLA DE MANDO (18) PARA INTRODUCIR UN RODILLO DE REPOSICION Y ESPIGA DE SUSTITUCION AHI DENTRO. LA ESPIGA DE SUSTITUCION SE SUJETA A LA VARILLA DE MANDO (18) POR MEDIO DE UNA SEXTA HERRAMIENTA (70F), SUSTENTADA SOBRE LA MESA GIRATORIA (68A), QUE ES TAMBIEN GRADUABLE EN POSICION.
ES93306461T 1992-08-19 1993-08-17 Aparato y procedimiento para el mantenimiento de barras de control. Expired - Lifetime ES2087661T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/932,175 US5243631A (en) 1992-08-19 1992-08-19 Control rod servicing apparatus and method

Publications (1)

Publication Number Publication Date
ES2087661T3 true ES2087661T3 (es) 1996-07-16

Family

ID=25461895

Family Applications (1)

Application Number Title Priority Date Filing Date
ES93306461T Expired - Lifetime ES2087661T3 (es) 1992-08-19 1993-08-17 Aparato y procedimiento para el mantenimiento de barras de control.

Country Status (5)

Country Link
US (1) US5243631A (es)
EP (1) EP0585031B1 (es)
DE (1) DE69302641T2 (es)
ES (1) ES2087661T3 (es)
TW (1) TW253060B (es)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4403149C2 (de) * 1994-02-17 1995-09-07 Herbert Wenzel Pneumatisch- und hydraulisch betätigter Bergegreifer für Kernkraftwerke und Industrie
JP3757122B2 (ja) * 2001-02-23 2006-03-22 株式会社日立製作所 沸騰水型原子炉用制御棒
TWI298156B (en) 2002-10-24 2008-06-21 Tian Holdings Llc Discrimination method for light storage device
CN100412972C (zh) 2003-09-15 2008-08-20 宇田控股有限公司 光盘片格式的辨识方法
US20050226114A1 (en) 2004-03-31 2005-10-13 Stanley Liow Method and apparatus for generating absolute time in pregroove data
US7570561B2 (en) 2004-05-25 2009-08-04 Bryan Tai Method for determining type of digital versatile discs
US7626907B2 (en) 2004-05-25 2009-12-01 Ricky Chang Method and apparatus for determining type of digital versatile disc
US7746745B2 (en) 2004-05-25 2010-06-29 Ricky Chang Method for determining the type of digital versatile disc
DE102008014544A1 (de) * 2008-03-15 2009-09-17 Areva Np Gmbh Vorrichtung zur Reparatur einer Schadstelle in einem unter Wasser befindlichen Wandbereich eines Behälters oder Beckens
CA2694883C (fr) * 2010-02-25 2016-08-09 Hydro-Quebec Robot pour usiner une piece de structure sous l'eau
US8867690B2 (en) * 2011-08-25 2014-10-21 Babcock & Wilcox Mpower, Inc. Pressurized water reactor with compact passive safety systems
CN109778789B (zh) * 2018-04-04 2020-08-25 水利部交通运输部国家能源局南京水利科学研究院 一种混凝土面板堆石坝面板脱空区水下修复系统

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5648586A (en) * 1979-09-29 1981-05-01 Tokyo Shibaura Electric Co Nuclear reactor control rod
JPS5952228B2 (ja) * 1980-07-09 1984-12-18 株式会社日立製作所 原子炉用摺動構造物
US4572710A (en) * 1982-06-14 1986-02-25 General Signal Corporation Method and apparatus for changing filters in nuclear power stations
SU1135697A1 (ru) * 1984-01-05 1985-01-23 Всесоюзный научно-исследовательский проектно-конструкторский технологический институт механизации труда в черной металлургии и ремонтно-механических работ Устройство дл замены роликов ленточного конвейера
SU1713701A1 (ru) * 1989-03-13 1992-02-23 Производственное объединение "Новокраматорский машиностроительный завод" Устройство дл смены валков прокатной клети
FR2658947B1 (fr) * 1990-02-28 1992-05-22 Cogema Enceinte mobile d'intervention permettant d'acceder a une installation placee dans une cellule active.

Also Published As

Publication number Publication date
TW253060B (es) 1995-08-01
DE69302641D1 (de) 1996-06-20
EP0585031A1 (en) 1994-03-02
DE69302641T2 (de) 1997-01-16
US5243631A (en) 1993-09-07
EP0585031B1 (en) 1996-05-15

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