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
Links
Classifications
-
- 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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B66—HOISTING; LIFTING; HAULING
- B66C—CRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
- B66C13/00—Other constructional features or details
- B66C13/18—Control systems or devices
- B66C13/46—Position indicators for suspended loads or for crane elements
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B66—HOISTING; LIFTING; HAULING
- B66C—CRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
- B66C13/00—Other constructional features or details
- B66C13/18—Control systems or devices
- B66C13/48—Automatic control of crane drives for producing a single or repeated working cycle; Programme control
-
- 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)
- 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)
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)
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)
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 |
-
1981
- 1981-07-27 US US06/287,102 patent/US4427623A/en not_active Expired - Lifetime
-
1982
- 1982-07-02 DE DE19823224700 patent/DE3224700A1/de active Granted
- 1982-07-14 IT IT8222383A patent/IT1210907B/it active
- 1982-07-21 ES ES514212A patent/ES8503451A1/es not_active Expired
- 1982-07-26 SE SE8204463A patent/SE449805B/sv not_active IP Right Cessation
- 1982-07-27 JP JP57129751A patent/JPS5837593A/ja active Granted
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 |