ES340578A1 - Handling facility for a nuclear reactor fuel recharging installation - Google Patents
Handling facility for a nuclear reactor fuel recharging installationInfo
- Publication number
- ES340578A1 ES340578A1 ES340578A ES340578A ES340578A1 ES 340578 A1 ES340578 A1 ES 340578A1 ES 340578 A ES340578 A ES 340578A ES 340578 A ES340578 A ES 340578A ES 340578 A1 ES340578 A1 ES 340578A1
- Authority
- ES
- Spain
- Prior art keywords
- arm
- vessel
- along
- motors
- gear wheel
- 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
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- 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
-
- 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
-
- 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
- G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
-
- 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
-
- 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
-
- 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)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Heat Treatment Of Articles (AREA)
Abstract
A fuelling apparatus for a sodium cooled fast reactor having a core 16 surrounded by a store 18 is completely removable from the reactor vessel 10 when not required for use and comprises a main beam A which may be advanced on rails (not shown) along an access gallery 20 when a vertically movable door 22 is raised to the open position shown. The extremity of the beam A rotatably supports the centre of a secondary beam B and when the beam A is introduced into the vessel 10, as shown, rollers 28 at the ends of the beam B rest on a circular track 30. A main carriage C traversible along the beam B supports an arm D through a pivotal joint, this joint enabling the arm to fold up against the beam B when the apparatus is withdrawn through the gallery 20 (Fig. 2, not shown). A secondary carriage E movable along the arm D carries grippers F for the fuel assemblies. The grippers F close automatically under spring pressure when lowered on to the head of a fuel assembly (Fig. 7, not shown) and are opened by a shaft and gear wheel transmission train driven by a motor. Other shaft and gear wheel transmission trains driven by motors are provided, respectively, for rotating the beam B and traversing the carriages C, E. These transmission trains are described with reference to Figs. 3-6 (not shown), all the motors being disposed on that part of the beam A which does not enter the vessel 10.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR61845A FR1497507A (en) | 1966-05-16 | 1966-05-16 | Handling device for nuclear reactor refueling installation |
Publications (1)
Publication Number | Publication Date |
---|---|
ES340578A1 true ES340578A1 (en) | 1969-05-16 |
Family
ID=8608801
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES340578A Expired ES340578A1 (en) | 1966-05-16 | 1967-05-16 | Handling facility for a nuclear reactor fuel recharging installation |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE697933A (en) |
CH (1) | CH476368A (en) |
ES (1) | ES340578A1 (en) |
FR (1) | FR1497507A (en) |
GB (1) | GB1119426A (en) |
LU (1) | LU53650A1 (en) |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2527826A1 (en) * | 1982-05-26 | 1983-12-02 | Commissariat Energie Atomique | DEVICE FOR CONTROLLING ABSORBENT BARS IN A NUCLEAR REACTOR DRIVER SYSTEM |
US4551299A (en) * | 1982-09-15 | 1985-11-05 | Westinghouse Electric Corp. | Multiple fuel rod gripper |
FR2638559A1 (en) * | 1988-10-28 | 1990-05-04 | Commissariat Energie Atomique | Handling plant for a fast-neutron nuclear reactor |
FR2647856B1 (en) * | 1989-05-31 | 1994-03-04 | Framatome | REMOTE CONTROLLED RELEASE AUXILIARY DEVICE FOR A POSITIVE ACTION MECHANISM |
CA3177167A1 (en) * | 2020-05-28 | 2021-12-02 | Bwxt Nuclear Energy, Inc. | Nuclear reactor fuel assemblies and process for production |
GB2600788A (en) * | 2021-04-19 | 2022-05-11 | Rolls Royce Plc | Refuelling of a nuclear reactor |
-
1966
- 1966-05-16 FR FR61845A patent/FR1497507A/en not_active Expired
-
1967
- 1967-05-03 BE BE697933D patent/BE697933A/xx unknown
- 1967-05-10 GB GB21786/67A patent/GB1119426A/en not_active Expired
- 1967-05-11 LU LU53650D patent/LU53650A1/xx unknown
- 1967-05-16 CH CH688267A patent/CH476368A/en not_active IP Right Cessation
- 1967-05-16 ES ES340578A patent/ES340578A1/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
LU53650A1 (en) | 1967-07-11 |
CH476368A (en) | 1969-07-31 |
BE697933A (en) | 1967-10-16 |
GB1119426A (en) | 1968-07-10 |
FR1497507A (en) | 1967-10-13 |
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