ES514212A0 - Metodo para desplazar automaticamente el puente y el carro rodante de una plataforma de reabastecimiento de combustible en una estructura de contencion de reactor nuclear. - Google Patents

Metodo para desplazar automaticamente el puente y el carro rodante de una plataforma de reabastecimiento de combustible en una estructura de contencion de reactor nuclear.

Info

Publication number
ES514212A0
ES514212A0 ES514212A ES514212A ES514212A0 ES 514212 A0 ES514212 A0 ES 514212A0 ES 514212 A ES514212 A ES 514212A ES 514212 A ES514212 A ES 514212A ES 514212 A0 ES514212 A0 ES 514212A0
Authority
ES
Spain
Prior art keywords
bridge
nuclear reactor
containment structure
reactor containment
rolling cart
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.)
Granted
Application number
ES514212A
Other languages
English (en)
Other versions
ES8503451A1 (es
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
Publication of ES514212A0 publication Critical patent/ES514212A0/es
Publication of ES8503451A1 publication Critical patent/ES8503451A1/es
Expired 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
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B66HOISTING; LIFTING; HAULING
    • B66CCRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
    • B66C13/00Other constructional features or details
    • B66C13/18Control systems or devices
    • B66C13/46Position indicators for suspended loads or for crane elements
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B66HOISTING; LIFTING; HAULING
    • B66CCRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
    • B66C13/00Other constructional features or details
    • B66C13/18Control systems or devices
    • B66C13/48Automatic control of crane drives for producing a single or repeated working cycle; Programme control
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Automation & Control Theory (AREA)
  • Mechanical Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Control And Safety Of Cranes (AREA)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
ES514212A 1981-07-27 1982-07-21 Metodo para desplazar automaticamente el puente y el carro rodante de una plataforma de reabastecimiento de combustible en una estructura de contencion de reactor nuclear. Expired ES8503451A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/287,102 US4427623A (en) 1981-07-27 1981-07-27 Automatic fuel transfer apparatus and method

Publications (2)

Publication Number Publication Date
ES514212A0 true ES514212A0 (es) 1985-02-16
ES8503451A1 ES8503451A1 (es) 1985-02-16

Family

ID=23101460

Family Applications (1)

Application Number Title Priority Date Filing Date
ES514212A Expired ES8503451A1 (es) 1981-07-27 1982-07-21 Metodo para desplazar automaticamente el puente y el carro rodante de una plataforma de reabastecimiento de combustible en una estructura de contencion de reactor nuclear.

Country Status (6)

Country Link
US (1) US4427623A (es)
JP (1) JPS5837593A (es)
DE (1) DE3224700A1 (es)
ES (1) ES8503451A1 (es)
IT (1) IT1210907B (es)
SE (1) SE449805B (es)

Families Citing this family (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3376706D1 (en) * 1983-09-06 1988-06-23 Acec Method and apparatus for supervising and controlling the fuel charging and discharging operations of a nuclear reactor
FR2591210A1 (fr) * 1985-12-11 1987-06-12 Metalliques Entrepr Cie Fse Installation de reglage de position pour un appareil de levage monte sur un pont roulant
EP0236816B1 (de) * 1986-03-04 1990-10-24 ABB Reaktor GmbH Verfahren und Einrichtung zur Unterstützung des Beladevorganges eines Reaktorkernes mit längserstreckten Brennelementen
DE3630058A1 (de) * 1986-03-04 1987-09-10 Bbc Reaktor Gmbh Verfahren und einrichtung zur unterstuetzung des beladevorganges eines reaktorkernes mit laengserstreckten brennelementen
DE3608636A1 (de) * 1986-03-14 1987-09-24 Kraftwerk Union Ag Nukleartechnische oder chemische einrichtung
US4699753A (en) * 1986-03-27 1987-10-13 Westinghouse Electric Corp. Reactor refueling machine simulator
JPH0664177B2 (ja) * 1986-09-26 1994-08-22 株式会社日立製作所 原子炉燃料交換機の制御方式
US5085824A (en) * 1991-01-31 1992-02-04 General Electric Company Nuclear refueling platform drive system
US5490185A (en) * 1993-07-23 1996-02-06 Westinghouse Electric Corporation System for automatic refueling of a nuclear reactor
US5369676A (en) * 1993-08-19 1994-11-29 General Electric Company Reactor refueling mechanism
JPH08262182A (ja) * 1995-03-27 1996-10-11 Hitachi Ltd 自動燃料交換装置
US5687207A (en) * 1996-04-02 1997-11-11 Westinghouse Electric Corporation Refueling machine
SE506569C2 (sv) * 1996-05-10 1998-01-12 Asea Atom Ab Metod och anordning vid rörelsekorrektion och positionering av en upphängningsanordning
SE509670C2 (sv) * 1996-05-10 1999-02-22 Asea Atom Ab Metod vid bränslehantering
US6856663B2 (en) * 2002-02-20 2005-02-15 General Electric Company Reactor servicing platform
US7032763B1 (en) * 2002-11-18 2006-04-25 Mi-Jack Products, Inc. System and method for automatically guiding a gantry crane
US20050013401A1 (en) * 2003-07-02 2005-01-20 Markling Robert E. Boiling water reactor refuel cavity work platform
JP4224784B2 (ja) * 2003-07-18 2009-02-18 株式会社ダイフク 把持部昇降式搬送装置
US9721686B2 (en) * 2006-12-29 2017-08-01 General Electric Company Handoff methods and assemblies for refueling a nuclear reactor
US7986760B2 (en) * 2007-11-15 2011-07-26 GE-Hitachi Nuclear Emergy Americas, LLC Method and apparatus for permissive control of a mast and grapple
US10854345B2 (en) * 2012-03-02 2020-12-01 Nuscale Power, Llc Servicing a nuclear reactor module
EP2973601B1 (en) * 2013-03-15 2018-09-26 BWXT mPower, Inc. Upper vessel transport
FR3059459B1 (fr) * 2016-11-25 2019-03-15 Electricite De France Optimisation de maintenance de centrale nucleaire
WO2020181017A1 (en) * 2019-03-04 2020-09-10 Ge-Hitachi Nuclear Energy Americas Systems and methods for underwater tool positioning
CN111285253B (zh) * 2020-01-22 2022-02-11 中联重科建筑起重机械有限责任公司 工程机械控制方法及控制装置

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3072554A (en) 1960-02-29 1963-01-08 Asea Ab Radiation protection means during the exchange of fuel elements
DE1227161B (de) * 1961-02-10 1966-10-20 Siemens Ag Atomreaktoranlage mit ferngesteuerter Belademaschine
US3431170A (en) 1966-12-07 1969-03-04 Gen Electric Nuclear reactor fuel bundle
US3904048A (en) 1968-12-02 1975-09-09 Asea Ab Device for refueling a nuclear reactor having a core comprising a plurality of fuel assemblies
US3734310A (en) 1970-08-12 1973-05-22 Aerojet General Co Stacker crane control system
US3927773A (en) 1972-06-19 1975-12-23 Thomas John Robert Bright Load storage system and apparatus therefor
US3817398A (en) 1973-01-22 1974-06-18 Transfer Systems Nuclear power cask handling system
US3863770A (en) 1973-04-11 1975-02-04 Westinghouse Electric Corp Method and apparatus for handling an irradiated fuel assembly
US3889169A (en) 1973-10-11 1975-06-10 Ibm Position and velocity servo control for motor controlled article carrier and handler
SU640915A1 (ru) 1975-07-09 1979-01-05 Всесоюзный Институт Технологии Строительного И Дорожного Машиностроения Устройство дл автоматического адресовани объекта
US4053356A (en) 1975-08-08 1977-10-11 Westinghouse Electric Corporation Guide device
JPS53105693A (en) * 1978-03-06 1978-09-13 Toshiba Corp Automatic fuel exchanging system of atomic power plant
JPS55109995A (en) * 1979-02-16 1980-08-23 Tokyo Shibaura Electric Co Automatically refueling device
JPS5612596A (en) * 1979-07-12 1981-02-06 Fuji Electric Co Ltd Control system of nuclear fuel exchanging device

Also Published As

Publication number Publication date
JPH0121477B2 (es) 1989-04-21
SE449805B (sv) 1987-05-18
SE8204463L (sv) 1983-01-28
JPS5837593A (ja) 1983-03-04
US4427623A (en) 1984-01-24
DE3224700C2 (es) 1988-08-25
IT1210907B (it) 1989-09-29
SE8204463D0 (sv) 1982-07-26
IT8222383A0 (it) 1982-07-14
DE3224700A1 (de) 1983-02-10
ES8503451A1 (es) 1985-02-16

Similar Documents

Publication Publication Date Title
ES514212A0 (es) Metodo para desplazar automaticamente el puente y el carro rodante de una plataforma de reabastecimiento de combustible en una estructura de contencion de reactor nuclear.
FI884518A (fi) Ydinpolttoaine-elementti sekä menetelmä ydinpolttoaineen komposiittiverhoussäiliön käsittelemiseksi
ES504164A0 (es) Metodo y su aparato correspondiente para inspeccionar pasti-llas de combustible destinadas a un reactor nuclear
ES513941A0 (es) Soporte de almacenamiento de combustible gastado de reactor nuclear.
DE69407459D1 (de) Plutonium zerstörender Kernreaktor mit Verwertung flüssigen Kernbrennstoffes
ES518748A0 (es) Perfeccionamientos en depositos para el almacenamiento a largo plazo de elementos combustibles quemados de reactores nucleares.
ES517737A0 (es) Aparato para retirar y-o posicionar los conjuntos de combustible de un reactor nuclear.
ES506070A0 (es) Estructura de combustible para reactor nuclear.
DE3176385D1 (en) Method and apparatus for inspecting nuclear fuel pellets
IT7827413A0 (it) Contenitore per il trasporto rispettivamente per l'immagazzinamento di sostanze radioattive, in particolare di elementi di combustione di reattore nucleare irradiati
ES490357A0 (es) Aparato para desplazar una barra de combustible desde un re-cipiente de almacenamiento en las rejas de un conjunto de combustible para reactor nuclear
FR2439461B1 (fr) Conteneur de securite avec dispositif protecteur contre les neutrons pour le transport et/ou le stockage d'elements combustibles nucleaires brules
DE3061029D1 (en) Method and apparatus for the control of fuel rods used in nuclear reactor assemblies
ES280868Y (es) Bastidor soporte de conjuntos de combustible en un reactor nuclear.
GB2096046B (en) Transport and storage flask for nuclear fuel
ES513501A0 (es) "aparato para sujetar y mantener un conjunto de combustible nuclear".
ES535427A0 (es) Un metodo de ensayar la interaccion entre pastillas y vaina de combustible nuclear.
JPS57182197A (en) Device for protecting leakage of fissionable gas in nuclear fuel rod
ES538745A0 (es) Aparato para elevar una varilla de combustible nuclear en un conjunto de combustible
ES510506A0 (es) Procedimiento para manipular y almacenar mediante un dispositivo sujetador elementos de combustible de un reactor nuclear.
ES276616Y (es) Pieza de soporte especialmente para la carga y-o descarga de los elementos combustibles de un reactor nuclear.
ES547886A0 (es) Recipiente blindado para almacenar combustible nuclear gas- tado
ES498660A0 (es) Perfeccionamientos en dispositivos para la reparacion de elementos combustibles de reactores nucleares de agua hir- viente
ZA968061B (en) Method and device for checking the characteristics of a surface layer of a zirconium-alloy ellement and use for the checking of fuel rods for a nuclear reactor.
BR8301330A (pt) Moderador de neutrons para a blindagem de neutrons e recipientes destinados ao armazenamento de combustiveis nucleares queimados

Legal Events

Date Code Title Description
MM4A Patent lapsed

Effective date: 19960401