ES8702055A1 - Perfeccionamientos en los sistemas de deteccion de defectos de estanqueidad de la vaina en un ensamblaje de combustible nuclear - Google Patents

Perfeccionamientos en los sistemas de deteccion de defectos de estanqueidad de la vaina en un ensamblaje de combustible nuclear

Info

Publication number
ES8702055A1
ES8702055A1 ES545916A ES545916A ES8702055A1 ES 8702055 A1 ES8702055 A1 ES 8702055A1 ES 545916 A ES545916 A ES 545916A ES 545916 A ES545916 A ES 545916A ES 8702055 A1 ES8702055 A1 ES 8702055A1
Authority
ES
Spain
Prior art keywords
sheaths
fuel assembly
nuclear fuel
detecting defective
water
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
ES545916A
Other languages
English (en)
Other versions
ES545916A0 (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.)
Fragema
Original Assignee
Fragema
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 Fragema filed Critical Fragema
Publication of ES545916A0 publication Critical patent/ES545916A0/es
Publication of ES8702055A1 publication Critical patent/ES8702055A1/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07Leak testing
    • 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

  • 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

MODIFICACIONES EN LOS SISTEMAS DE DETECCION DE DEFECTOS DE ESTANQUEIDAD DE LA VAINA DE UN ENSAMBLAJE DE COMBUSTIBLE NUCLEAR. CONSISTENT4ES EN PREVEER: UN BUCLE (12) DE AGUA Y UN BUCLE (14) DE GAS QUE TIENEN, EN EL ALVEOLO (34), UNA PARTE COMUN QUE COMPRENDE UN FILTRO HOMOGENEIZADOR DISPUESTO EN LA PARTE BAJA DEL ALVEOLO Y ELEMENTOS PARA INYECTAR AGUA Y GAS EN (34) POR DEBAJO DEL FILTRO; Y UNA PARTE ABOCARGADA (36) EN LA QUE TERMINA SUPERIORMENTE (34), COLOCADA EN UNA CAJA DE AGUA Y DE SEPARACION GAS-AGUA PROVISTA DE UNA CONEXION SUPERIOR (60) DE SALIDA DE GAS Y DE UNA TOMA LATERAL (33) DE EXTRACCION DE AGUA. APLICABLE COMO CONTROL POR RESUDACION DE LA ESTANQUEIDAD DE LAS VAINAS DE UN ENSAMBLAJE DE COMBUSTIBLE NUCLEAR.
ES545916A 1984-08-08 1985-08-06 Perfeccionamientos en los sistemas de deteccion de defectos de estanqueidad de la vaina en un ensamblaje de combustible nuclear Expired ES8702055A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR8412561A FR2569041B1 (fr) 1984-08-08 1984-08-08 Procede et dispositif de controle par ressuage de l'etancheite des gaines d'un assemblage de combustible nucleaire

Publications (2)

Publication Number Publication Date
ES545916A0 ES545916A0 (es) 1986-12-16
ES8702055A1 true ES8702055A1 (es) 1986-12-16

Family

ID=9306919

Family Applications (1)

Application Number Title Priority Date Filing Date
ES545916A Expired ES8702055A1 (es) 1984-08-08 1985-08-06 Perfeccionamientos en los sistemas de deteccion de defectos de estanqueidad de la vaina en un ensamblaje de combustible nuclear

Country Status (4)

Country Link
US (1) US4696788A (es)
ES (1) ES8702055A1 (es)
FR (1) FR2569041B1 (es)
SE (1) SE459291B (es)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2634049B1 (fr) * 1988-07-06 1991-05-24 Electricite De France Procede et dispositif d'identification du defaut d'etancheite d'un crayon absorbeur de neutrons d'un reacteur nucleaire
FR2666924B1 (fr) * 1990-09-13 1992-12-18 Framatome Sa Procede et dispositif de detection de fuite sur un element combustible d'un assemblage pour reacteur nucleaire.
DE4238563C2 (de) * 1991-05-17 2002-01-03 Asea Atom Ab Verfahren zur Leckstellenprüfung von Brennelementen für Siedewasserreaktoren
US5546435A (en) * 1992-11-16 1996-08-13 Abb Atom Ab Fission product leak detection in a pressurized-water reactor
US5414742A (en) * 1993-11-10 1995-05-09 Westinghouse Electric Corporation Leak-detection system and method for detecting a leaking container
EP0677853B2 (en) 1994-04-15 2005-12-14 General Electric Company System for detection of defective nuclear fuel rod
CA2147705A1 (en) * 1994-04-25 1996-04-18 Ralph Walter Tolino Leak-detection system and method for detecting an individual leaking nuclear fuel rod having radioactive material leaking therefrom
US5570400A (en) * 1995-08-08 1996-10-29 B&W Fuel Company On line sipping air delivery system
US5706319A (en) * 1996-08-12 1998-01-06 Joseph Oat Corporation Reactor vessel seal and method for temporarily sealing a reactor pressure vessel from the refueling canal
US5754610A (en) * 1996-12-05 1998-05-19 Framatome Technologies, Inc. In-mast sipping modular mast modification
SE514184C2 (sv) * 1997-11-21 2001-01-22 Asea Atom Ab Förfarande och anordning för utvärdering av integriteten hos kärnbränslet i en nukleär anläggning
US6345082B1 (en) 1999-06-03 2002-02-05 Thomas A. Galioto Fuel assembly mechanical flow restriction apparatus for detecting failure in situ of nuclear fuel rods in a fuel assembly during reactor shutdown
SE520391C2 (sv) * 2001-08-23 2003-07-01 Westinghouse Atom Ab Förfarande och anordning för utvärdering av integriteten av en styrsubstans i en nukleär anläggning
US8737557B2 (en) 2006-07-21 2014-05-27 Areva Inc. Method for prediction of light water reactor fuel defects using a fuel condition index
DE102017114835B3 (de) * 2017-07-04 2018-10-31 Framatome Gmbh Analysevorrichtung zum Nachweis von Spaltprodukten durch Messung einer Radioaktivität und Analysesystem

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3073767A (en) * 1959-06-08 1963-01-15 Whitham George Kirby Reactor fuel elements testing container
DE2258727A1 (de) * 1972-11-30 1974-06-06 Siemens Ag Verfahren fuer das zonenweise umsetzen von kernreaktorbrennelementen
DE2304324A1 (de) * 1973-01-30 1974-08-01 Interatom Vorrichtung zur ueberpruefung von brennelementen fluessigkeitsgekuehlter kernreaktoren auf huellrohrschaeden
US4034599A (en) * 1975-06-18 1977-07-12 General Electric Company Device for locating defective fuel
JPS52106096A (en) * 1976-03-03 1977-09-06 Hitachi Ltd Broken fuel detecting method
FR2389202A1 (fr) * 1977-04-29 1978-11-24 Framatome Sa Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant
JPS5555293A (en) * 1978-10-20 1980-04-23 Hitachi Ltd Failed fuel detector
DE2931336C2 (de) * 1979-08-02 1983-08-04 Rheinisch-Westfälisches Elektrizitätswerk AG, 4300 Essen Verfahren zum Erkennen von Undichtigkeiten in Brennstoffumhüllungen abgebrannter Kernreaktor-Brennelemente und Inspektionsbehälter zur Durchführung des Verfahrens
JPS5629199A (en) * 1979-08-20 1981-03-23 Hitachi Ltd Method and device of detecting failed fuel
FR2509897A1 (fr) * 1981-07-17 1983-01-21 Commissariat Energie Atomique Procede de detection et d'estimation de la grandeur d'une fissure dans la gaine d'un crayon d'assemblage combustible de reacteur nucleaire
US4537740A (en) * 1983-03-31 1985-08-27 The United States Of America As Represented By The United States Department Of Energy Fission gas detection system

Also Published As

Publication number Publication date
ES545916A0 (es) 1986-12-16
US4696788A (en) 1987-09-29
SE459291B (sv) 1989-06-19
SE8503721D0 (sv) 1985-08-06
FR2569041A1 (fr) 1986-02-14
FR2569041B1 (fr) 1987-01-02
SE8503721L (sv) 1986-02-09

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