ES2087687T3 - Procedimiento y dispositivo de reparacion de la superficie interior de un adaptador que atraviesa la tapa de la cuba de un reactor nuclear. - Google Patents
Procedimiento y dispositivo de reparacion de la superficie interior de un adaptador que atraviesa la tapa de la cuba de un reactor nuclear.Info
- Publication number
- ES2087687T3 ES2087687T3 ES93402551T ES93402551T ES2087687T3 ES 2087687 T3 ES2087687 T3 ES 2087687T3 ES 93402551 T ES93402551 T ES 93402551T ES 93402551 T ES93402551 T ES 93402551T ES 2087687 T3 ES2087687 T3 ES 2087687T3
- Authority
- ES
- Spain
- Prior art keywords
- adapter
- procedure
- exudation
- repairing
- crossing
- 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 - Lifetime
Links
- 238000000034 method Methods 0.000 title abstract 2
- 238000006073 displacement reaction Methods 0.000 abstract 2
- 230000001680 brushing effect Effects 0.000 abstract 1
- 238000004140 cleaning Methods 0.000 abstract 1
- 238000001514 detection method Methods 0.000 abstract 1
- 238000003466 welding Methods 0.000 abstract 1
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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
- G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
- G21C17/01—Inspection of the inner surfaces of vessels
-
- 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49718—Repairing
- Y10T29/49721—Repairing with disassembling
- Y10T29/49723—Repairing with disassembling including reconditioning of part
- Y10T29/49725—Repairing with disassembling including reconditioning of part by shaping
- Y10T29/49726—Removing material
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)
- Instruments For Viewing The Inside Of Hollow Bodies (AREA)
- Manipulator (AREA)
- Working Measures On Existing Buildindgs (AREA)
Abstract
SE EJECUTA UNA DETECCION Y UN CONTROL DE FISURAS (135) SOBRE LA SUPERFICIE INTERNA DEL ADAPTADOR (2), AL MENOS EN UNA ZONA PROXIMA DE LA SOLDADURA DE FIJACION DEL ADAPTADOR (2) MEDIANTE OPERACIONES DE CONTROL A DISTANCIA, QUE IMPLICAN AL MENOS UN CONTROL DE EXUDACION, CON EXAMEN ENDOSCOPICO A DISTANCIA DE FISURAS (135) OBSERVADAS POR LA EXUDACION. SE REALIZA MEDIANTE UN PROCEDIMIENTO MECANIZADO AL MENOS UNA SOCAVACION (136) DE UNA PROFUNDIDAD DETERMINADA DE LA SUPERFICIE INTERNA DEL ADAPTADOR QUE TIENE UNA FISURA (135). SEGUN EL RESULTADO DEL CONTROL POR LA EXUDACION, SE PRACTICA O NO UNA RECARGA DE LA ZONA (136) DESPUES DE LA SOCAVACION. EL DISPOSITIVO ADMITE UN CONJUNTO DE DESPLAZAMIENTO EN TRASLACION Y EN ROTACION EN EL INTERIOR DEL ADAPTADOR, DE UN VASTAGO EN CUYO EXTREMO SE PUEDEN FIJAR MEDIOS DE BROCHADO, DE LIMPIEZA O DE ASPERSION, UN DISPOSITIVO DE DESPLAZAMIENTO DE UN SOPORTE DE ENDOSCOPIO EN EL INTERIOR DEL ADAPTADOR Y UN UTILLAJE DE EJECUCION DEL MECANIZADO DE LA SUPERFICIE INTERIOR DEL ADAPTADOR.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR9213693A FR2698206B1 (fr) | 1992-11-13 | 1992-11-13 | Procédé et dispositif de réparation de la surface intérieure d'un adaptateur traversant le couvercle de la cuve d'un réacteur nucléaire. |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| ES2087687T3 true ES2087687T3 (es) | 1996-07-16 |
Family
ID=9435530
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES93402551T Expired - Lifetime ES2087687T3 (es) | 1992-11-13 | 1993-10-15 | Procedimiento y dispositivo de reparacion de la superficie interior de un adaptador que atraviesa la tapa de la cuba de un reactor nuclear. |
Country Status (4)
| Country | Link |
|---|---|
| US (2) | US5396525A (es) |
| EP (1) | EP0598634B1 (es) |
| ES (1) | ES2087687T3 (es) |
| FR (1) | FR2698206B1 (es) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5611948A (en) * | 1994-10-31 | 1997-03-18 | Westinghouse Electric Corporation | Apparatus and method for remotely positioning a probe in a tubular member |
| US5515589A (en) * | 1994-12-27 | 1996-05-14 | General Electric Company | In situ method for remotely operated, automatic contour mapping, machining and welding of piping |
| FR2826172B1 (fr) * | 2001-06-14 | 2003-09-19 | Framatome Anp | Procede et dispositif de restauration du temps de chute d'au moins une grappe de commande de reglage de la reactivite dans le coeur d'un reacteur nucleaire refroidi par de l'eau legere |
| FR2902569B1 (fr) * | 2006-06-16 | 2008-09-12 | Areva Np Sas | Procede de reparation d'une penetration de fond de cuve d'un reacteur nucleaire |
| US7971497B2 (en) | 2007-11-26 | 2011-07-05 | Air Products And Chemicals, Inc. | Devices and methods for performing inspections, repairs, and/or other operations within vessels |
| GB2474834B (en) | 2009-10-28 | 2013-09-11 | Rolls Royce Plc | A method of inspecting and/or repairing component and a device for inspecting and/or repairing a component |
| FR2993188B1 (fr) * | 2012-07-12 | 2014-07-11 | Snecma | Dispositif de pulverisation d'un produit de ressuage sur une piece |
| US9909704B2 (en) * | 2015-02-03 | 2018-03-06 | Chevron U.S.A. Inc. | Non-welded apparatus for providing access to the interior of an enclosure and methods for use thereof |
| CN106328228B (zh) * | 2015-07-10 | 2018-02-13 | 中核武汉核电运行技术股份有限公司 | 一种传热管密封焊遥控自动渗透检查装置 |
| US12027278B2 (en) * | 2019-02-25 | 2024-07-02 | Westinghouse Electric Company Llc | Anti-rotation arrangement for thermal sleeves |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| NL172790C (nl) * | 1978-01-20 | 1983-10-17 | Roentgen Tech Dienst Bv | Inrichting voor het onderzoeken van lassen. |
| DE2810487A1 (de) * | 1978-03-10 | 1979-09-13 | Kraftwerk Union Ag | Pruefeinrichtung |
| JPS5518962A (en) * | 1978-07-27 | 1980-02-09 | Hitachi Ltd | Device for detecting in nuclear reactor vessel |
| FR2656147B1 (fr) * | 1989-12-15 | 1992-04-10 | Electricite De France | Procede de remplacement d'element chauffant de pressuriseur de reacteur nucleaire et dispositif utilise dans un tel procede. |
| US5115136A (en) * | 1990-08-06 | 1992-05-19 | Olympus Corporation | Ultraviolet remote visual inspection system |
| US5317607A (en) * | 1993-04-30 | 1994-05-31 | Combustion Engineering, Inc. | EDM crack removal tooling |
-
1992
- 1992-11-13 FR FR9213693A patent/FR2698206B1/fr not_active Expired - Fee Related
-
1993
- 1993-10-15 ES ES93402551T patent/ES2087687T3/es not_active Expired - Lifetime
- 1993-10-15 EP EP93402551A patent/EP0598634B1/fr not_active Expired - Lifetime
- 1993-11-15 US US08/151,840 patent/US5396525A/en not_active Expired - Fee Related
-
1994
- 1994-09-30 US US08/312,944 patent/US5434895A/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| US5434895A (en) | 1995-07-18 |
| EP0598634A1 (fr) | 1994-05-25 |
| FR2698206B1 (fr) | 1995-03-03 |
| FR2698206A1 (fr) | 1994-05-20 |
| EP0598634B1 (fr) | 1996-05-15 |
| US5396525A (en) | 1995-03-07 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| FG2A | Definitive protection |
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