ES8403235A1 - Aparato para agrupar a distancia barras de combustible nuclear. - Google Patents

Aparato para agrupar a distancia barras de combustible nuclear.

Info

Publication number
ES8403235A1
ES8403235A1 ES512535A ES512535A ES8403235A1 ES 8403235 A1 ES8403235 A1 ES 8403235A1 ES 512535 A ES512535 A ES 512535A ES 512535 A ES512535 A ES 512535A ES 8403235 A1 ES8403235 A1 ES 8403235A1
Authority
ES
Spain
Prior art keywords
station
spent fuel
fuel assembly
fuel rods
spent
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
Application number
ES512535A
Other languages
English (en)
Other versions
ES512535A0 (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.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
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 claimed from US06/268,225 external-priority patent/US4446098A/en
Priority claimed from US06/268,311 external-priority patent/US4441242A/en
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of ES512535A0 publication Critical patent/ES512535A0/es
Publication of ES8403235A1 publication Critical patent/ES8403235A1/es
Expired legal-status Critical Current

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
    • G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • 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
    • G21C19/06—Magazines for holding fuel elements or control elements
    • 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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • 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
    • 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
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

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)
  • Load-Engaging Elements For Cranes (AREA)

Abstract

APARATO DE AGRUPACION DE COMBUSTIBLE GASTADO PARA DESMANTELAR EN SENTIDO VERTICAL Y A DISTANCIA UN CONJUNTO DE COMBUSTIBLE NUCLEAR IRRADIADO, MIENTRAS DICHO CONJUNTO DE COMBUSTIBLE ESTA INMERSO EN UN REFRIGERANTE Y, PARA AGRUPAR LAS BARRAS DE COMBUSTIBLE GASTADAS DEL CONJUNTO DE COMBUSTIBLE DESMANTELADO.CONSTA DE UNA PLATAFORMA (20) MONTADA DE MANERA GIRATORIA SOBRE UN SOPORTE VERTICAL (22) QUE INCLUYE UN PUESTO DE CONJUNTO DE COMBUSTIBLE (24), UN PUESTO DE AGRUPAMIENTO (26) Y UN PUESTO DE RECEPTACULO (28) CONECTADO CON DICHA PLATAFORMA (20); Y DE UN MECANISMODE AGARRE (32) QUE ESTA DISPUESTO DE MANERA MOVIL SOBRE EL SOPORTE VERTICAL (22) PARA TRANSFERIR LAS BARRAS DE COMBUSTIBLE GASTADAS (40) DESDE UN PUESTO HASTA OTRO.
ES512535A 1981-05-29 1982-05-25 Aparato para agrupar a distancia barras de combustible nuclear. Expired ES8403235A1 (es)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US06/268,225 US4446098A (en) 1981-05-29 1981-05-29 Spent fuel consolidation system
US06/268,311 US4441242A (en) 1981-05-29 1981-05-29 Spent fuel consolidation system

Publications (2)

Publication Number Publication Date
ES512535A0 ES512535A0 (es) 1984-03-01
ES8403235A1 true ES8403235A1 (es) 1984-03-01

Family

ID=26952954

Family Applications (1)

Application Number Title Priority Date Filing Date
ES512535A Expired ES8403235A1 (es) 1981-05-29 1982-05-25 Aparato para agrupar a distancia barras de combustible nuclear.

Country Status (5)

Country Link
EP (1) EP0066695B1 (es)
KR (1) KR890002385B1 (es)
DE (1) DE3268629D1 (es)
ES (1) ES8403235A1 (es)
FR (1) FR2506993B1 (es)

Families Citing this family (27)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4775507A (en) * 1981-08-10 1988-10-04 U.S. Tool & Die, Inc. Method for compacting spent nuclear reactor fuel rods
FR2528218A1 (fr) * 1982-06-07 1983-12-09 Transnucleaire Procede, installation et dispositif pour le compactage d'objets oblongs et flexibles notamment des crayons combustibles de reacteur nucleaire
US4537711A (en) * 1983-01-05 1985-08-27 Westinghouse Electric Corp. Fuel assembly skeleton compaction
DE3331761A1 (de) * 1983-09-02 1985-03-21 Siemens AG, 1000 Berlin und 8000 München Druckvorrichtung zum ausschieben von brennstaeben aus einem kernreaktor-brennelement
US4547117A (en) * 1983-09-23 1985-10-15 Westinghouse Electric Corp. Nuclear fuel rod bundle drive apparatus
JPS60123799A (ja) * 1983-12-08 1985-07-02 株式会社神戸製鋼所 使用済燃料内挿物の減容処理装置
DE3344738C2 (de) * 1983-12-10 1986-10-30 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Zerlegbares Brennelement für Kernreaktoren
DE3416620C2 (de) * 1984-05-05 1986-05-07 Transnuklear Gmbh, 6450 Hanau Unterwasser-Zerkleinerungsvorrichtung
DE3417742A1 (de) * 1984-05-12 1985-11-14 Steag Kernenergie Gmbh, 4300 Essen Verfahren zum deassemblieren von brennelementen und vorrichtung zur durchfuehrung des verfahrens
US4667547A (en) * 1984-09-26 1987-05-26 Westinghouse Electric Corp. Apparatus and method for removing a top nozzle in reconstituting a fuel assembly
EP0186161A3 (en) * 1984-12-24 1987-12-02 Combustion Engineering, Inc. Canister for consolidation of nuclear fuel rods
DE3505242A1 (de) * 1985-02-15 1986-08-21 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Verfahren und vorrichtung zur vereinzelung von brennstaeben eines brennelementes
DE3506584A1 (de) * 1985-02-25 1986-08-28 Kraftwerk Union AG, 4330 Mülheim Einrichtung zum einsetzen von kernbrennstoff oder neutronenabsorberstoff enthaltenden staeben in einer vorgegebenen dichten packung in einen behaelter
ES8801470A1 (es) * 1985-06-20 1988-01-01 Westinghouse Electric Corp Dispositivo destinado a ser utilizado en un haz de barras de combustible como las de un generador nuclear
FR2586854B1 (fr) * 1985-08-29 1987-12-04 Framatome Sa Procede et dispositif de compactage d'un faisceau de crayons de combustibles
FR2591021B1 (fr) * 1985-12-02 1988-02-26 Cogema Dispositif de prehension d'un faisceau de crayons d'un assemblage de combustible nucleaire
FR2596565B1 (fr) * 1986-04-01 1988-07-01 Cogema Procede de mise en etui d'un faisceau de crayons d'un assemblage de combustible nucleaire et installation pour la mise en oeuvre de ce procede
US4723359A (en) * 1986-06-13 1988-02-09 Westinghouse Electric Corp. Spent fuel rod horizontal consolidation system and method
FR2609834A1 (fr) * 1987-01-19 1988-07-22 Us Tool Die Inc Procede et appareil pour regrouper des barres de combustible epuise de reacteurs nucleaires
BE1000261A3 (fr) * 1987-01-20 1988-09-27 Us Tool & Die Procede et appareil pour regrouper des barres de combustible epuise de reacteurs nucleaires.
DE3711844A1 (de) * 1987-04-08 1988-10-27 Wiederaufarbeitung Von Kernbre Vorrichtung zum herausziehen von mehreren brennstaeben aus einem brennelement
DE3802966A1 (de) * 1987-10-02 1989-04-20 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zur behandlung eines von brennstaeben befreiten brennelementskelettes eines bestrahlten kernreaktorbrennelementes
US4842809A (en) * 1988-04-15 1989-06-27 The Babcock & Wilcox Company Vertical close pack rod arraying system
EP0355191A1 (de) * 1988-08-24 1990-02-28 Siemens Aktiengesellschaft Vorrichtung zum Einsetzen von Brennstäben in eine Büchse
FR2673033B1 (fr) * 1991-02-19 1994-07-22 Framatome Sa Procede et dispositif de demantelement des equipements internes d'un reacteur nucleaire refroidi par de l'eau.
SE509671C2 (sv) * 1996-11-22 1999-02-22 Asea Atom Ab Metod och anordning vid bränslehantering
RU2477899C1 (ru) * 2011-12-08 2013-03-20 Федеральное государственное унитарное предприятие "Горно-химический комбинат" Чехол для размещения и хранения отработавших тепловыделяющих сборок реактора ввэр-1000

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3352003A (en) * 1961-11-21 1967-11-14 Combustion Eng Method of fabricating a fuel element cluster
US3827579A (en) * 1968-03-25 1974-08-06 Gen Electric Irradiated fuel processing system
US3748713A (en) * 1968-08-19 1973-07-31 Atomic Energy Authority Uk Apparatus for inserting rods into a frame
US3586603A (en) * 1968-10-10 1971-06-22 Atomic Energy Commission Nuclear fuel rod having an offset plenum
US3763770A (en) * 1970-12-15 1973-10-09 Allied Chem Method for shearing spent nuclear fuel bundles
LU78579A1 (es) * 1976-11-27 1978-04-20
US4139778A (en) * 1977-02-02 1979-02-13 Westinghouse Electric Corp. Swivel base for fuel assembly storage
ZA791691B (en) * 1978-05-15 1980-07-30 Westinghouse Electric Corp Arrangement for storing spent nuclear fuel rods at a reactor site

Also Published As

Publication number Publication date
ES512535A0 (es) 1984-03-01
FR2506993A1 (fr) 1982-12-03
FR2506993B1 (fr) 1988-05-20
DE3268629D1 (en) 1986-03-06
EP0066695A3 (en) 1983-04-20
EP0066695B1 (en) 1986-01-22
EP0066695A2 (en) 1982-12-15
KR890002385B1 (ko) 1989-07-02

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19971001