FR2506993A1 - Systeme de consolidation de combustible epuise - Google Patents

Systeme de consolidation de combustible epuise

Info

Publication number
FR2506993A1
FR2506993A1 FR8209179A FR8209179A FR2506993A1 FR 2506993 A1 FR2506993 A1 FR 2506993A1 FR 8209179 A FR8209179 A FR 8209179A FR 8209179 A FR8209179 A FR 8209179A FR 2506993 A1 FR2506993 A1 FR 2506993A1
Authority
FR
France
Prior art keywords
station
fuel
bars
assembly
exhausted
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
FR8209179A
Other languages
English (en)
Other versions
FR2506993B1 (fr
Inventor
Michael Graham Hicken
Fred Kirschensteiner
Duane Alan True
Alexander Taleff
Paul Pomaibo
Ralph Walter Tolino
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 US06/268,311 external-priority patent/US4441242A/en
Priority claimed from US06/268,225 external-priority patent/US4446098A/en
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of FR2506993A1 publication Critical patent/FR2506993A1/fr
Application granted granted Critical
Publication of FR2506993B1 publication Critical patent/FR2506993B1/fr
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

L'APPAREIL DE CONSOLIDATION DE COMBUSTIBLE EPUISE SELON LA PRESENTE INVENTION EST DESTINE A DEMANTELER A DISTANCE UN ASSEMBLAGE COMBUSTIBLE NUCLEAIRE IRRADIE PENDANT QUE CET ASSEMBLAGE EST IMMERGE DANS UN FLUIDE REFRIGERANT ET A GROUPER DE FACON SERREE LES BARRES DE COMBUSTIBLE. CET APPAREIL COMPREND UNE PLATE-FORME 20 MONTEE DE FACON TOURNANTE SUR UN SUPPORT VERTICAL 22, UN POSTE 24 A ASSEMBLAGE COMBUSTIBLE, UN POSTE DE CONSOLIDATION 26 ET UN POSTE 28 A CONTENEUR ETANT FIXE A LA PLATE-FORME 20. UN MECANISME DE PREHENSION 32 EST DISPOSE DE FACON MOBILE SUR LE SUPPORT VERTICAL 22 EN VUE DE TRANSFERER LES BARRES 40 DE COMBUSTIBLE EPUISE D'UN POSTE A UN AUTRE AU FUR ET A MESURE QUE LES DIVERS POSTES TOURNENT ET VIENNENT S'ALIGNER AVEC CE MECANISME. AU POSTE A ASSEMBLAGE COMBUSTIBLE, UN ASSEMBLAGE COMBUSTIBLE 38 EST MAINTENU EN POSITION PENDANT QUE LES BARRES 40 DE COMBUSTIBLE EPUISE EN SONT ENLEVEES. DANS LE POSTE DE CONSOLIDATION 26 LES BARRES DE COMBUSTIBLE EPUISE SONT TASSEES LES UNES CONTRE LES AUTRES ET, DANS LE POSTE A CONTENEUR, LES BARRES DE COMBUSTIBLE TASSEES SONT MAINTENUES ETROITEMENT GROUPEES.
FR8209179A 1981-05-29 1982-05-26 Systeme de consolidation de combustible epuise Expired FR2506993B1 (fr)

Applications Claiming Priority (2)

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

Publications (2)

Publication Number Publication Date
FR2506993A1 true FR2506993A1 (fr) 1982-12-03
FR2506993B1 FR2506993B1 (fr) 1988-05-20

Family

ID=26952954

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8209179A Expired FR2506993B1 (fr) 1981-05-29 1982-05-26 Systeme de consolidation de combustible epuise

Country Status (5)

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

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2673033A1 (fr) * 1991-02-19 1992-08-21 Framatome Sa Procede et dispositif de demantelement des equipements internes d'un reacteur nucleaire refroidi par de l'eau.

Families Citing this family (26)

* 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
DE3417742C2 (de) * 1984-05-12 1987-04-09 Steag Kernenergie Gmbh, 4300 Essen Verfahren zum Zerlegen von Kernreaktor-Brennelementen und Vorrichtung zur Durchführung 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 (fr) * 1984-12-24 1987-12-02 Combustion Engineering, Inc. Boíte de consolidation pour barres de combustible nucléaire
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 (fr) * 1988-08-24 1990-02-28 Siemens Aktiengesellschaft Dispositif de mise en étui de barreaux combustibles
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

Citations (6)

* 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
FR2117928A1 (fr) * 1970-12-15 1972-07-28 Allied Chem
US3748713A (en) * 1968-08-19 1973-07-31 Atomic Energy Authority Uk Apparatus for inserting rods into a frame
US3827579A (en) * 1968-03-25 1974-08-06 Gen Electric Irradiated fuel processing system
LU78579A1 (fr) * 1976-11-27 1978-04-20
EP0005623A2 (fr) * 1978-05-15 1979-11-28 Westinghouse Electric Corporation Recipient de stockage de barres usées de combustible nucléaire dans une installation à réacteur nucléaire

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3586603A (en) * 1968-10-10 1971-06-22 Atomic Energy Commission Nuclear fuel rod having an offset plenum
US4139778A (en) * 1977-02-02 1979-02-13 Westinghouse Electric Corp. Swivel base for fuel assembly storage

Patent Citations (6)

* 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
FR2117928A1 (fr) * 1970-12-15 1972-07-28 Allied Chem
LU78579A1 (fr) * 1976-11-27 1978-04-20
EP0005623A2 (fr) * 1978-05-15 1979-11-28 Westinghouse Electric Corporation Recipient de stockage de barres usées de combustible nucléaire dans une installation à réacteur nucléaire

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2673033A1 (fr) * 1991-02-19 1992-08-21 Framatome Sa Procede et dispositif de demantelement des equipements internes d'un reacteur nucleaire refroidi par de l'eau.
EP0500404A1 (fr) * 1991-02-19 1992-08-26 Framatome Procédé et dispositif de démentèlement des équipements internes d'un réacteur nucléaire refroidi par de l'eau
US5263062A (en) * 1991-02-19 1993-11-16 Framatome Process and apparatus for dismantling the internal equipment of a water-cooled nuclear reactor

Also Published As

Publication number Publication date
EP0066695A3 (en) 1983-04-20
ES512535A0 (es) 1984-03-01
FR2506993B1 (fr) 1988-05-20
EP0066695B1 (fr) 1986-01-22
DE3268629D1 (en) 1986-03-06
KR890002385B1 (ko) 1989-07-02
EP0066695A2 (fr) 1982-12-15
ES8403235A1 (es) 1984-03-01

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ST Notification of lapse