FR2399098A1 - DEVICE FOR EXTRACTING FROM THE ACTIVE ZONE OF A NUCLEAR REACTOR THE FUEL ASSEMBLIES AND THE COVERS OF THE CONTROL AND PROTECTION SYSTEMS - Google Patents
DEVICE FOR EXTRACTING FROM THE ACTIVE ZONE OF A NUCLEAR REACTOR THE FUEL ASSEMBLIES AND THE COVERS OF THE CONTROL AND PROTECTION SYSTEMSInfo
- Publication number
- FR2399098A1 FR2399098A1 FR7723536A FR7723536A FR2399098A1 FR 2399098 A1 FR2399098 A1 FR 2399098A1 FR 7723536 A FR7723536 A FR 7723536A FR 7723536 A FR7723536 A FR 7723536A FR 2399098 A1 FR2399098 A1 FR 2399098A1
- Authority
- FR
- France
- Prior art keywords
- extracted
- extracting
- covers
- control
- nuclear reactor
- 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.)
- Granted
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
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
- G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Load-Engaging Elements For Cranes (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Manipulator (AREA)
Abstract
L'invention concerne la technique nucléaire. Le dispositif faisant l'objet de l'invention est caractérisé en ce que l'alésage de la barre creuse 6 a un diamètre qui lui permet de s'engager sur l'élément à extraire 4, et qu'à celle des extrémités de la barre 6 qui est orientée vers l'élément à extraire 4, est monté un grappin supplémentaire 10 destiné à coopérer avec la surface extérieure de l'élément à extraire 4, ladite barre ayant une longueur suffisante pour que le grappin supplémentaire 10 atteigne l'extrémité de l'élément à extraire 4 opposée à la tête de celui-ci, quand le grappin principal 7 est engagé sur ladite tête. L'invention s'applique notamment aux réacteurs à neutrons rapides, refroidi par métal liquide.The invention relates to nuclear technology. The device forming the subject of the invention is characterized in that the bore of the hollow bar 6 has a diameter which allows it to engage on the element to be extracted 4, and that of the ends of the bar 6 which is oriented towards the element to be extracted 4, is mounted an additional grapple 10 intended to cooperate with the outer surface of the element to be extracted 4, said bar having a sufficient length for the additional grapple 10 to reach the end of the element to be extracted 4 opposite the head thereof, when the main gripper 7 is engaged on said head. The invention applies in particular to fast neutron reactors, cooled by liquid metal.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB7721986A GB1542363A (en) | 1977-05-25 | 1977-05-25 | Nuclear reactors |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2399098A1 true FR2399098A1 (en) | 1979-02-23 |
FR2399098B1 FR2399098B1 (en) | 1980-02-22 |
Family
ID=10172089
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7723536A Granted FR2399098A1 (en) | 1977-05-25 | 1977-07-29 | DEVICE FOR EXTRACTING FROM THE ACTIVE ZONE OF A NUCLEAR REACTOR THE FUEL ASSEMBLIES AND THE COVERS OF THE CONTROL AND PROTECTION SYSTEMS |
Country Status (3)
Country | Link |
---|---|
DE (1) | DE2726759C3 (en) |
FR (1) | FR2399098A1 (en) |
GB (1) | GB1542363A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3110582A1 (en) * | 1981-03-18 | 1982-10-14 | Kraftwerk Union AG, 4330 Mülheim | METHOD FOR THE MANIPULATION AND / OR STORAGE OF A LONG-EXTENDED SKELETON WITH FUEL RODS AND NUCLEAR REACTOR FUEL ELEMENT AND NUCLEAR REACTOR FUEL ELEMENT, IN PARTICULAR FOR THIS METHOD |
FR2588689A1 (en) * | 1985-10-11 | 1987-04-17 | Fragema Framatome & Cogema | NUCLEAR FUEL ASSEMBLY HANDLING MACHINE AND REACTOR LOADING METHOD THEREOF |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3942387A1 (en) * | 1989-12-21 | 1991-06-27 | Florian Fischer | TRANSPORT SYSTEM, ESPECIALLY FOR TRANSPORTING SILICONE SINGLE CRYSTALS BY BOWLING A RESEARCH REACTOR |
CN113211341A (en) * | 2021-04-02 | 2021-08-06 | 江苏核电有限公司 | Anti-slip protection clamp for nuclear detection detector and anti-slip method thereof |
-
1977
- 1977-05-25 GB GB7721986A patent/GB1542363A/en not_active Expired
- 1977-06-14 DE DE2726759A patent/DE2726759C3/en not_active Expired
- 1977-07-29 FR FR7723536A patent/FR2399098A1/en active Granted
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3110582A1 (en) * | 1981-03-18 | 1982-10-14 | Kraftwerk Union AG, 4330 Mülheim | METHOD FOR THE MANIPULATION AND / OR STORAGE OF A LONG-EXTENDED SKELETON WITH FUEL RODS AND NUCLEAR REACTOR FUEL ELEMENT AND NUCLEAR REACTOR FUEL ELEMENT, IN PARTICULAR FOR THIS METHOD |
FR2588689A1 (en) * | 1985-10-11 | 1987-04-17 | Fragema Framatome & Cogema | NUCLEAR FUEL ASSEMBLY HANDLING MACHINE AND REACTOR LOADING METHOD THEREOF |
EP0220117A1 (en) * | 1985-10-11 | 1987-04-29 | Framatome | Nuclear-fuel assembly-handling machine and method for reactor refueling comprising its application |
Also Published As
Publication number | Publication date |
---|---|
GB1542363A (en) | 1979-03-14 |
DE2726759C3 (en) | 1980-11-20 |
DE2726759A1 (en) | 1978-12-21 |
DE2726759B2 (en) | 1980-03-20 |
FR2399098B1 (en) | 1980-02-22 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |