ES2069047T3 - Procedimiento de reemplazado de elemento calefactor de presurizador de reactor nuclear y dispositivo utilizado en dicho procedimiento. - Google Patents
Procedimiento de reemplazado de elemento calefactor de presurizador de reactor nuclear y dispositivo utilizado en dicho procedimiento.Info
- Publication number
- ES2069047T3 ES2069047T3 ES90403615T ES90403615T ES2069047T3 ES 2069047 T3 ES2069047 T3 ES 2069047T3 ES 90403615 T ES90403615 T ES 90403615T ES 90403615 T ES90403615 T ES 90403615T ES 2069047 T3 ES2069047 T3 ES 2069047T3
- Authority
- ES
- Spain
- Prior art keywords
- procedure
- heater
- nuclear reactor
- sleeve
- heating element
- 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 4
- 238000010438 heat treatment Methods 0.000 title 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/09—Pressure regulating arrangements, i.e. pressurisers
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K9/00—Arc welding or cutting
- B23K9/02—Seam welding; Backing means; Inserts
- B23K9/028—Seam welding; Backing means; Inserts for curved planar seams
- B23K9/0282—Seam welding; Backing means; Inserts for curved planar seams for welding tube sections
- B23K9/0286—Seam welding; Backing means; Inserts for curved planar seams for welding tube sections with an electrode moving around the fixed tube during the welding operation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Butt Welding And Welding Of Specific Article (AREA)
- Arc Welding In General (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Automatic Assembly (AREA)
- Pressure Vessels And Lids Thereof (AREA)
- Die Bonding (AREA)
Abstract
PROCEDIMIENTO DE SUSTITUCION DE ELEMENTO QUE CALIENTA, DE PRESURIZADOR DE REACTOR NUCLEAR DE AGUA BAJO PRESION Y DISPOSITIVO UTILIZADO EN DICHO PROCEDIMIENTO SEGUN EL CUAL, DESPUES DE QUITAR EL ELEMENTO QUE CALIENTA QUE HAY QUE SUSTITUIR, SE SUELDA AUTOMATICAMENTE BAJO ATMOSFERA INERTE O SENSIBLEMENTE INERTE, LA CARA INTERNA DE LA EXTREMIDAD (23) DE LA TUBERIA DE SALIDA DEL ELEMENTO QUE CALIENTA DEL PRESURIZADOR, CON LA CARA INTERNA DE LA EXTREMIDAD SUPERIOR DE UN MANGUITO (27), SE SUELDA AUTOMATICAMENTE BAJO ATMOSFERA INERTE LA CARA EXTERNA DE LA EXTREMIDAD (23) DE DICHA TUBERIA CON LA CARA EXTERNA DE LA EXTREMIDAD SUPERIOR DE DICHO MANGUITO (27), SE INTRODUCE EN LA CUBA, VIA EL MANGUITO Y LA TUBERIA CORRESPONDIENTE, EL ELEMENTO QUE CALIENTA NUEVO (6") Y SE SUELDA AUTOMATICAMENTE LA CARA EXTERNA DE LA EXTREMIDAD SUPERIOR DE LOS MEDIOS DE TOPE (9") DEL ELEMENTO QUE CALIENTA (6") CON LA CARA EXTERNA DE LA EXTREMIDAD INFERIOR DEL MANGUITO.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR8916657A FR2656147B1 (fr) | 1989-12-15 | 1989-12-15 | Procede de remplacement d'element chauffant de pressuriseur de reacteur nucleaire et dispositif utilise dans un tel procede. |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| ES2069047T3 true ES2069047T3 (es) | 1995-05-01 |
Family
ID=9388586
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES90403615T Expired - Lifetime ES2069047T3 (es) | 1989-12-15 | 1990-12-14 | Procedimiento de reemplazado de elemento calefactor de presurizador de reactor nuclear y dispositivo utilizado en dicho procedimiento. |
Country Status (5)
| Country | Link |
|---|---|
| EP (1) | EP0433179B1 (es) |
| AT (1) | ATE119307T1 (es) |
| DE (1) | DE69017393T2 (es) |
| ES (1) | ES2069047T3 (es) |
| FR (1) | FR2656147B1 (es) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2698206B1 (fr) * | 1992-11-13 | 1995-03-03 | Framatome Sa | Procédé et dispositif de réparation de la surface intérieure d'un adaptateur traversant le couvercle de la cuve d'un réacteur nucléaire. |
| FR2700981B1 (fr) * | 1993-01-29 | 1995-04-21 | Framatome Sa | Procédé et dispositif de soudage orbital d'une pièce cylindrique sur une paroi courbe. |
| JP3496031B2 (ja) * | 1993-07-05 | 2004-02-09 | 株式会社フジキン | 超高純度ガス供給系配管の溶接方法 |
| FR2711007B1 (fr) * | 1993-10-04 | 1995-12-29 | Electricite De France | Dispositif d'extraction de cannes chauffantes d'un pressuriseur de centrale nucléaire. |
| US5396039A (en) * | 1993-11-24 | 1995-03-07 | L'air Liquide, Societe Anonyme Pour L'etude Et L'exploitation Des Procedes Georges Claude | Process for assembling piping or components by TIG welding |
| FR2723869A1 (fr) * | 1994-08-30 | 1996-03-01 | Framatome Sa | Procede de reparation d'une liaison soudee heterogene entre une tubulure d'un composant d'un reacteur nucleaire et une tuyauterie. |
| FR2723870B1 (fr) * | 1994-08-30 | 1996-11-15 | Framatome Sa | Procede de reparation d'une liaison soudee heterogene entre une tubulure d'un composant d'un reacteur nucleaire et une tuyauterie. |
| FR2742369B1 (fr) * | 1995-12-18 | 1998-03-06 | Framatome Sa | Procede de raccordement par soudage heterogene de deux pieces et utilisation |
| ES2147476B1 (es) * | 1996-11-20 | 2001-04-01 | Frimetal S A | Metodo y cabezal para union de piezas de tubos de acero inoxidable. |
| FR2802014B1 (fr) * | 1999-12-01 | 2002-03-01 | Framatome Sa | Procede et dispositif de montage et de fixation par soudage d'une canne chauffante d'un pressuriseur d'un reacteur nucleaire refroidi par de l'eau sous pression |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB929118A (en) * | 1958-07-30 | 1963-06-19 | Foster Wheeler Ltd | Improvements in the butt welding of tubes |
| GB1035199A (en) * | 1962-12-10 | 1966-07-06 | Superheater Co Ltd | Improvements in or relating to methods of electric arc butt welding |
| US3688069A (en) * | 1970-11-23 | 1972-08-29 | Gasparas Kazlauskas | Welding head apparatus |
| US3818786A (en) * | 1972-12-21 | 1974-06-25 | Combustion Eng | Remote cutting apparatus |
| CS206794B1 (en) * | 1979-04-09 | 1981-06-30 | Karel Tvrdy | Apparatus for transversal seams automatic welding at weldment hole |
| FR2540575B1 (fr) * | 1983-02-04 | 1986-07-18 | Electricite De France | Dispositif de raccordement etanche d'un element plongeur a une enceinte, notamment pour raccorder des elements plongeurs chauffants au pressuriseur d'une centrale nucleaire a eau pressurisee |
-
1989
- 1989-12-15 FR FR8916657A patent/FR2656147B1/fr not_active Expired - Lifetime
-
1990
- 1990-12-14 AT AT90403615T patent/ATE119307T1/de not_active IP Right Cessation
- 1990-12-14 ES ES90403615T patent/ES2069047T3/es not_active Expired - Lifetime
- 1990-12-14 EP EP90403615A patent/EP0433179B1/fr not_active Expired - Lifetime
- 1990-12-14 DE DE69017393T patent/DE69017393T2/de not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| DE69017393T2 (de) | 1995-10-19 |
| DE69017393D1 (de) | 1995-04-06 |
| ATE119307T1 (de) | 1995-03-15 |
| FR2656147B1 (fr) | 1992-04-10 |
| FR2656147A1 (fr) | 1991-06-21 |
| EP0433179A1 (fr) | 1991-06-19 |
| EP0433179B1 (fr) | 1995-03-01 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE3864172D1 (de) | Verfahren und einrichtung zur druckentlastung eines kernkraftwerkes. | |
| ES8502282A1 (es) | Procedimiento y dispositivo de sustitucion de los pernos de guia de un tubo de guia de un reactor nuclear de agua a presion | |
| ES2069047T3 (es) | Procedimiento de reemplazado de elemento calefactor de presurizador de reactor nuclear y dispositivo utilizado en dicho procedimiento. | |
| DE3274697D1 (en) | Process and apparatus for the volume reduction of pressurized water reactor liquid wastes | |
| JPS5518962A (en) | Device for detecting in nuclear reactor vessel | |
| JPS53134776A (en) | Method and apparatus for detecting leak portions in hollow fiber modules employed for liquid treatments | |
| IL48203A (en) | Method and apparatus for controlling fluid pressure drop within a nuclear reactor fuel element | |
| FI940590A7 (fi) | Menetelmä ja laite näytteiden ottamiseksi kaasutiiviisti suljetun säiliön ilmakehästä, erityisesti ydinvoimalaitoksen reaktorivarmuussäiliöstä | |
| FR2530366B1 (fr) | Procede pour le confinement etanche au gaz d'elements radioactifs et installation pour la mise en oeuvre dudit procede | |
| DE58906300D1 (de) | Heizreaktorsystem mit einer Nachwärmeabfuhr-Schaltung und Verwendung letzterer für Siedewasser- und Druckwasser-Kernreaktoren. | |
| ATE59492T1 (de) | Verfahren zum einsetzen eines stabbuendels eines kernbrennstoffbuendels in einen behaelter und anlage zur durchfuehrung dieses verfahrens. | |
| ZA896589B (en) | Device and process for the fitting of a blocking sleeve of a guide tube in a removable connector of a fuel assembly of a nuclear reactor | |
| DE3464173D1 (en) | Apparatus for connecting an immersion element to a high pressure vessel, method of connecting and disconnecting the apparatus and jack for carrying out the method | |
| JPS53123796A (en) | Processing method of nuclear fuel and processing apparatus used for said method | |
| EG16629A (en) | Process and device for modifying the concentration of the soluble poison contained in the cooling fluid of a nuclear reactor | |
| AU6363290A (en) | Nuclear oxygen activation method and apparatus for detecting and quantifying water flow | |
| DE69108640D1 (de) | Zentriervorrichtung zur Verwendung während des Austausches der Brennelemente von wassergekühlten Kernreaktoren. | |
| DE3167063D1 (en) | Apparatus to reduce thermal stresses in the sleeve of a device steeping in liquid alkaline metal coolant in a fast breeder nuclear reactor | |
| FR2656731B1 (fr) | Procede et dispositif de remplacement d'une canne chauffante d'un pressuriseur d'un reacteur nucleaire a eau sous pression. | |
| JPS5540977A (en) | Method and apparatus for decontaminating nuclear reactor pressure container nozzle | |
| JPS5430398A (en) | Device for removing clad in core | |
| JPS5651696A (en) | Nuclear reactor feedwater device * and its operation method | |
| DE3262471D1 (en) | Coupling device for control rods in nuclear reactors | |
| JPS5758095A (en) | Heat transfer tube support | |
| JPS57125887A (en) | Supporting device for nuclear reactor pressure vessel |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| FG2A | Definitive protection |
Ref document number: 433179 Country of ref document: ES |