ZA834433B - Process for the replacement of guide pins of a guiding tube forming part of the top internal equipment of a pressurised water nuclear reactor,and corresponding apparatus - Google Patents
Process for the replacement of guide pins of a guiding tube forming part of the top internal equipment of a pressurised water nuclear reactor,and corresponding apparatusInfo
- Publication number
- ZA834433B ZA834433B ZA834433A ZA834433A ZA834433B ZA 834433 B ZA834433 B ZA 834433B ZA 834433 A ZA834433 A ZA 834433A ZA 834433 A ZA834433 A ZA 834433A ZA 834433 B ZA834433 B ZA 834433B
- Authority
- ZA
- South Africa
- Prior art keywords
- replacement
- forming part
- nuclear reactor
- guide pins
- guiding tube
- Prior art date
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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/334—Assembling, maintenance or repair of the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/53—Means to assemble or disassemble
- Y10T29/531—Nuclear device
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Treatment Of Steel In Its Molten State (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR8213751A FR2531563A1 (fr) | 1982-08-06 | 1982-08-06 | Procede de remplacement des broches de guidage d'un tube-guide faisant partie des equipements internes superieurs d'un reacteur nucleaire a eau sous pression et dispositif correspondant |
Publications (1)
Publication Number | Publication Date |
---|---|
ZA834433B true ZA834433B (en) | 1984-03-28 |
Family
ID=9276692
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ZA834433A ZA834433B (en) | 1982-08-06 | 1983-06-16 | Process for the replacement of guide pins of a guiding tube forming part of the top internal equipment of a pressurised water nuclear reactor,and corresponding apparatus |
Country Status (8)
Country | Link |
---|---|
US (2) | US4585613A (es) |
JP (1) | JPS5946885A (es) |
KR (1) | KR900009108B1 (es) |
BE (1) | BE897468A (es) |
DE (1) | DE3327726C2 (es) |
ES (1) | ES524781A0 (es) |
FR (1) | FR2531563A1 (es) |
ZA (1) | ZA834433B (es) |
Families Citing this family (29)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0130840A3 (en) * | 1983-07-01 | 1985-05-29 | Quadrex Corporation | Alignment pin for guide tube assembly in nuclear power plant reactor vessel |
US4770846A (en) * | 1984-02-03 | 1988-09-13 | Westinghouse Electric Corp. | Replacement support pin for guide tubes in operating plants |
US4675961A (en) * | 1984-06-06 | 1987-06-30 | Westinghouse Electric Corp. | Replacement of split-pin assemblies in guide tubes |
EP0165735A3 (en) * | 1984-06-06 | 1987-09-23 | Westinghouse Electric Corporation | Replacement of split pins in guide tubes |
US4624042A (en) * | 1984-06-06 | 1986-11-25 | Westinghouse Electric Corp. | Robotic clamp and index tool and method for their use in repairing certain elements with in a nuclear reactor |
US4672162A (en) * | 1984-06-06 | 1987-06-09 | Westinghouse Electric Corp. | Electric arc apparatus for severing split-pin assemblies of guide tubes of nuclear reactors |
EP0164991A3 (en) * | 1984-06-06 | 1987-09-16 | Westinghouse Electric Corporation | Metal disintegration machining apparatus |
US4720898A (en) * | 1984-06-06 | 1988-01-26 | Westinghouse Electric Corp. | Replacement of split pins in guide tubes |
US4704246A (en) * | 1984-06-06 | 1987-11-03 | Westinghouse Electric Corp. | Crimping |
US4772448A (en) * | 1986-01-07 | 1988-09-20 | Westinghouse Electric Corp. | Support pin system and locking nut retainer |
FR2595501B1 (fr) * | 1986-03-07 | 1988-06-10 | Framatome Sa | Equipements internes de reacteurs nucleaires a cuve allongee |
US4756067A (en) * | 1986-07-31 | 1988-07-12 | Westinghouse Electric Corp. | Manual replacement of old split-pin assemblies by new split-pin assemblies |
US4748733A (en) * | 1986-08-29 | 1988-06-07 | Westinghouse Electric Corp. | Removal of old split-pin assemblies from guide tubes and replacement by new split-pin assemblies |
US4738820A (en) * | 1986-11-21 | 1988-04-19 | Westinghouse Electric Corp. | Nuclear fuel assembly bottom nozzle attachment system allowing reconstitution |
US4820479A (en) * | 1988-02-10 | 1989-04-11 | Westinghouse Electric Corp. | Guide pin assembly for a nuclear reactor |
US5001818A (en) * | 1988-09-30 | 1991-03-26 | Westinghouse Electric Corp. | Underwater milling machine system for core barrel repair |
US4937039A (en) * | 1989-01-17 | 1990-06-26 | Westinghouse Electric Corp. | Four pin mounting system for nuclear reactor control rod guide tubes |
FR2645328B1 (fr) * | 1989-04-04 | 1991-07-19 | Framatome Sa | Dispositif de centrage d'un outil d'intervention dans un tube de generateur de vapeur |
FR2651363B1 (fr) * | 1989-08-31 | 1993-11-26 | Framatome | Dispositif de serrage controle a distance d'un ecrou d'une broche de positionnement d'un tube-guide des equipements internes d'un reacteur nucleaire a eau sous pression. |
US5207980A (en) * | 1991-10-27 | 1993-05-04 | Westinghouse Electric Corp. | Top nozzle-mounted replacement guide pin assemblies |
DE9314732U1 (de) * | 1993-09-29 | 1993-12-09 | Siemens AG, 80333 München | Vorrichtung zum Lösen einer Schraubenverbindung eines Steuerstabantriebes |
US6026137A (en) * | 1996-08-09 | 2000-02-15 | Westinghouse Electric Corporation | Control rod guide tube mounting pin |
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 |
FR2841367B1 (fr) | 2002-06-11 | 2005-03-18 | Framatome Anp | Dispositif de positionnement et d'alignement axial d'un assemblage de combustible et procede et dispositif de reconstitution d'un element de positionnement |
FR2840722B1 (fr) * | 2002-06-11 | 2004-09-10 | Framatome Anp | Procede et dispositif de reconstitution d'un element de positionnement d'un assemblage de combustible sur une plaque de support de coeur d'un reacteur nucleaire |
DE102006047394A1 (de) * | 2006-10-06 | 2008-04-10 | Robert Bosch Gmbh | Verfahren zur Herstellung eines Verbundbauteils und metall-keramisches Verbundbauteil |
FR2931581B1 (fr) * | 2008-05-23 | 2015-01-02 | Comex Nucleaire | Procede de remplacement des broches de centrage des tubes de guides de grappes sur la plaque superieure de coeur d'un reacteur nucleaire |
JP5730156B2 (ja) * | 2011-08-12 | 2015-06-03 | 三菱重工業株式会社 | 制御棒クラスタ案内管の支持ピン交換装置 |
CN103921099B (zh) * | 2014-04-10 | 2016-02-17 | 中国船舶重工集团公司第七○二研究所 | 大直径深海模拟器卡箍装卸装置 |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3904048A (en) * | 1968-12-02 | 1975-09-09 | Asea Ab | Device for refueling a nuclear reactor having a core comprising a plurality of fuel assemblies |
US3887980A (en) * | 1973-03-29 | 1975-06-10 | Exxon Nuclear Co Inc | Nuclear fuel bundle disassembly and assembly tool |
US4208247A (en) * | 1977-08-15 | 1980-06-17 | Westinghouse Electric Corp. | Neutron source |
US4272321A (en) * | 1978-06-01 | 1981-06-09 | Combustion Engineering, Inc. | Nuclear reactor internals and control rod handling device |
US4207723A (en) * | 1978-06-14 | 1980-06-17 | General Atomic Company | Canning and inspection system for nuclear reactor fuel and reflector elements |
FR2487106A1 (fr) * | 1980-07-15 | 1982-01-22 | Commissariat Energie Atomique | Installation de remplacement d'un organe d'un circuit de fluide contamine et procede de remplacement de cet organe |
FR2488033A1 (fr) * | 1980-07-31 | 1982-02-05 | Framatome Sa | Dispositif de protection des mecanismes de commande des grappes de controle pendant les essais d'un reacteur nucleaire |
FR2495816A1 (fr) * | 1980-12-05 | 1982-06-11 | Framatome Sa | Machine pour le controle sur leur poste de stockage des equipements internes d'un reacteur nucleaire |
US4575930A (en) * | 1983-12-21 | 1986-03-18 | Westinghouse Electric Corp. | Nuclear reactor fuel assembly peripheral rod lifting device |
-
1982
- 1982-08-06 FR FR8213751A patent/FR2531563A1/fr active Granted
-
1983
- 1983-06-16 ZA ZA834433A patent/ZA834433B/xx unknown
- 1983-06-29 US US06/509,116 patent/US4585613A/en not_active Expired - Fee Related
- 1983-07-14 KR KR1019830003212A patent/KR900009108B1/ko not_active IP Right Cessation
- 1983-08-01 DE DE3327726A patent/DE3327726C2/de not_active Expired
- 1983-08-04 JP JP58143092A patent/JPS5946885A/ja active Granted
- 1983-08-04 BE BE0/211306A patent/BE897468A/fr not_active IP Right Cessation
- 1983-08-05 ES ES524781A patent/ES524781A0/es active Granted
-
1985
- 1985-06-06 US US06/741,916 patent/US4656734A/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
DE3327726A1 (de) | 1984-02-09 |
US4656734A (en) | 1987-04-14 |
ES8502282A1 (es) | 1984-12-16 |
ES524781A0 (es) | 1984-12-16 |
KR900009108B1 (ko) | 1990-12-22 |
KR840005893A (ko) | 1984-11-19 |
DE3327726C2 (de) | 1986-04-24 |
US4585613A (en) | 1986-04-29 |
JPS5946885A (ja) | 1984-03-16 |
FR2531563B1 (es) | 1985-03-22 |
FR2531563A1 (fr) | 1984-02-10 |
JPH037276B2 (es) | 1991-02-01 |
BE897468A (fr) | 1984-02-06 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ZA834433B (en) | Process for the replacement of guide pins of a guiding tube forming part of the top internal equipment of a pressurised water nuclear reactor,and corresponding apparatus | |
DE3167872D1 (en) | Fuel-element bundle for a nuclear reactor | |
ZA822517B (en) | Emergency cooling device for a pressurized water nuclear reactor | |
ZA84209B (en) | Apparatus for screwing-unscrewing,particularly for screwing-unscrewing the stud-bolts fixing the cover of the reactor vessel of a nuclear reactor | |
GB2157060B (en) | Retaining pin for nuclear reactor guide tube mounts | |
DE3469087D1 (en) | Hold-down apparatus for a nuclear reactor | |
GB2014888B (en) | Apparatus and method for guiding a ring structure during the manufacture thereof | |
ZA832073B (en) | Process for treating a polymerisation reactor | |
EP0291286A3 (en) | Guide roller assembly for nuclear reactor refueling apparatus | |
GB2070454B (en) | Method for treating a nuclear process off-gas stream | |
DE3164333D1 (en) | Manufacturing process for a nuclear reactor vessel ring | |
ZA803396B (en) | Method and apparatus for fixing a guide tube of a nuclear reactor fuel assembly | |
DE3462308D1 (en) | Process and apparatus for the ultrafiltration of cooling water of a pressurized-water nuclear reactor | |
ZA834202B (en) | Method of operating a reactor for the production of synthesis gas and apparatus for implementing the method | |
DE3171852D1 (en) | Apparatus for controlling internal equipment of a nuclear reactor in its storage position | |
ZA827885B (en) | Device for cooling the primary circuit of a pressurised water nuclear reactor | |
GB1557105A (en) | Method for refuelling a nuclear reactor core | |
DE3379521D1 (en) | Method and apparatus for the surveillance of the reactivity rate of a core in a nuclear reactor and for the diagnosis of changes in the core reactivity | |
DE3172053D1 (en) | Fuel-element bundle for a nuclear reactor | |
DE3160354D1 (en) | Primary circuit pressure-control method during the shut-down period of a pressurised water nuclear reactor | |
DE3462963D1 (en) | Process for operating a nuclear reactor | |
DE3061937D1 (en) | Guiding apparatus for servicing-ducts for the small, rotatable lid of a nuclear reactor | |
DE3169629D1 (en) | Method and device for cooling the primary circuit of a pressurized water reactor | |
ZA821620B (en) | Guide apparatus for a rigid starting bar | |
JPS5769294A (en) | Main steam guide device of nuclear reactor |