ES348820A1 - Refuelling apparatus for a nuclear reactor - Google Patents
Refuelling apparatus for a nuclear reactorInfo
- Publication number
- ES348820A1 ES348820A1 ES348820A ES348820A ES348820A1 ES 348820 A1 ES348820 A1 ES 348820A1 ES 348820 A ES348820 A ES 348820A ES 348820 A ES348820 A ES 348820A ES 348820 A1 ES348820 A1 ES 348820A1
- Authority
- ES
- Spain
- Prior art keywords
- arm
- manipulator
- container
- fuel elements
- grab
- 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
- 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
- G21C19/18—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
- G21C19/32—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)
- Manipulator (AREA)
- Load-Engaging Elements For Cranes (AREA)
Abstract
A reactor core 10 situated within shielding 12 constituting the pressure vessel is refuelled by apparatus A situated within the pressure vessel and separated from the core by a partition 20, apertures (not shown) in the partition and closable by plugs permitting the grab (not shown) of a manipulator 44 to react the fuel channels in the core. The apparatus A comprises a main arm 22 rotatable about the vertical axis of the reactor and supported by rollers 24, 26, 28 engaging three circular tracks, the arm being driven by a motor 30 through a pinion 34 engaging an annular toothed wheel 36 connected to the arm. Motor means on the manipulator 44 enable it to be displaced along the arm 22 and also control the grab. The outer end of the arm 22 carries a container 40 having sufficient cells to receive all the fuel elements of one channel, the inner end of the arm carrying a container 38 for receiving the plugs closing an aperture in the partition 20. In use, the manipulator 44 traverses to and fro along the arm to place the plugs from a selected aperture by means of the grab, into the container 38. Further to and fro movement of the manipulator enables the grab to place the fuel elements of the selected channel into the container 40. The spent fuel elements are removed from the container 40 by apparatus B comprising a tunnel 46 carrying a track 52. A duct 64 from the tunnel leads to a vessel 66 in a compartment 76 having a hoist 78. In use, the arm 22 is aligned with the track 52 and the manipulator 44 removes the fuel elements from the container 40 and lowers them into the vessel 66. Subsequently, the hoist 78 removes the fuel elements from the vessel 66 and lowers them through a duct 82 to a spent fuel store. To provide against breakdown there is a duplicate tunnel and manipulator and a shorter rotatable arm 221 in the pressure vessel may be aligned with the main arm 22 so that the duplicate manipulator may be transferred on to the arm 22 supporting the failed manipulator, the failed manipulator then being moved on to a track 54 in a lock formed by valves 48, 50.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR90096A FR1519664A (en) | 1967-01-05 | 1967-01-05 | Nuclear reactor fuel reloading facility |
Publications (1)
Publication Number | Publication Date |
---|---|
ES348820A1 true ES348820A1 (en) | 1969-07-16 |
Family
ID=8623432
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES348820A Expired ES348820A1 (en) | 1967-01-05 | 1967-12-30 | Refuelling apparatus for a nuclear reactor |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE707540A (en) |
CH (1) | CH489091A (en) |
ES (1) | ES348820A1 (en) |
FR (1) | FR1519664A (en) |
GB (1) | GB1143329A (en) |
LU (1) | LU55188A1 (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2431752A1 (en) * | 1978-07-20 | 1980-02-15 | Commissariat Energie Atomique | Enclosure confining water-cooled nuclear reactor - has partitions radiating from central column forming compartments serving as fuel assemblage storage pond and borated water reservoir |
FR2558636B1 (en) * | 1984-01-19 | 1989-03-03 | Commissariat Energie Atomique | FAST NEUTRAL NUCLEAR REACTOR HAVING A HANDLING CELL AND A BOX SLAB |
CN104766640B (en) * | 2015-03-05 | 2017-10-24 | 中国核电工程有限公司 | A kind of nuclear fuel rapid transport device |
-
1967
- 1967-01-05 FR FR90096A patent/FR1519664A/en not_active Expired
- 1967-12-05 BE BE707540D patent/BE707540A/xx unknown
- 1967-12-11 CH CH1731867A patent/CH489091A/en not_active IP Right Cessation
- 1967-12-14 GB GB56763/67A patent/GB1143329A/en not_active Expired
- 1967-12-29 LU LU55188A patent/LU55188A1/xx unknown
- 1967-12-30 ES ES348820A patent/ES348820A1/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
FR1519664A (en) | 1968-04-05 |
BE707540A (en) | 1968-04-16 |
LU55188A1 (en) | 1968-03-06 |
GB1143329A (en) | 1969-02-19 |
CH489091A (en) | 1970-04-15 |
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