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 nuclearInfo
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
- G21C17/07—Leak testing
-
- 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
- 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.
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)
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)
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 |
-
1984
- 1984-08-08 FR FR8412561A patent/FR2569041B1/fr not_active Expired
-
1985
- 1985-08-06 SE SE8503721A patent/SE459291B/sv not_active IP Right Cessation
- 1985-08-06 ES ES545916A patent/ES8702055A1/es not_active Expired
- 1985-08-08 US US06/763,732 patent/US4696788A/en not_active Expired - Lifetime
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 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES8702055A1 (es) | Perfeccionamientos en los sistemas de deteccion de defectos de estanqueidad de la vaina en un ensamblaje de combustible nuclear | |
JPS5746145A (en) | Method of and apparatus for inspecting flaws of fuel pellets for nuclear reactor | |
GB2080943B (en) | Inspecting fuel pellets for nuclear reactor | |
DE3264214D1 (en) | Apparatus for converting a fuel into combustible gas | |
JPS56141539A (en) | Detector for nuclear reactor fuel pellet | |
ZM3880A1 (en) | Sprinkler burner and method of introducing particulate material and gas into a reactor | |
PH19907A (en) | Method and apparatus for detecting defective elements in a nuclear reactor fuel assembly | |
JPS56163190A (en) | Method and apparatus for gasifying carbonaceous matter for fuel gas manufacture | |
JPS5797022A (en) | High degree detecting and controlling apparatus for gas turbine engine | |
GB2098235B (en) | Process for increasing the calorific value of fuel gas mixtures containing hydrogen | |
ES517499A0 (es) | Procedimiento y dispositivo de interrogacion de un detector de contenido de gas combustible. | |
IL55685A (en) | Procedure and equipment for injecting gas into liquids such as nuclear reactor coolant | |
GB1524002A (en) | Nuclear reactor containment spray testing system | |
GB2008552B (en) | Process for the production of particles of fertile material or of fuel and fertile material for fuel elements of nuclear reactors | |
KR860004419A (ko) | 원자로 조립체의 핵 연료 요소 누설감지 방법 및 장치 | |
JPS5574495A (en) | Method of detecting and measuring failure characteristic of reactor fuel cladding | |
FR2509898B1 (fr) | Procede de detection rapide d'une fissure dans la gaine d'un crayon combustible d'un assemblage de reacteur nucleaire | |
ES8702044A1 (es) | Procedimiento de explotacion de un reactor nuclear de agua ligera | |
JPS57148294A (en) | Method of separating laminated nuclear fuel particle from graphite matrix high-temperature gas reactor fuel and plant therefor | |
PL255037A1 (en) | Method of obtaining gas from carbon containing fuels and reactor therefor | |
DE3169827D1 (en) | Installation and method for handling fuel assemblies in a fast breeder reactor | |
GB2147453B (en) | Process for lowering the reactivity of a gas-cooled, graphite-moderated nuclear reactor, and graphite element with shut -down substance therein | |
DE3279212D1 (en) | Device for detecting ruptures in the cladding of fuel assemblies of a fast breeder reactor | |
YU40950B (en) | Arrangament for on aconstic detection of fuel conplexes of a nuclear reactor on which defects appeared durinf the operation in the rreactor | |
ES459712A1 (es) | Procedimiento y dispositivo para detectar y prelocalizar unarotura de funda dentro de un reactor nuclear de neutrones rapidos. |