GB1117265A - A fuel charging installation for a nuclear reactor - Google Patents
A fuel charging installation for a nuclear reactorInfo
- Publication number
- GB1117265A GB1117265A GB42168/66A GB4216866A GB1117265A GB 1117265 A GB1117265 A GB 1117265A GB 42168/66 A GB42168/66 A GB 42168/66A GB 4216866 A GB4216866 A GB 4216866A GB 1117265 A GB1117265 A GB 1117265A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel assembly
- sleeve
- rod
- core
- duct
- 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
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- 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
- G21C19/11—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with revolving coupling elements, e.g. socket coupling
-
- 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
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Other Liquid Machine Or Engine Such As Wave Power Use (AREA)
- Jib Cranes (AREA)
Abstract
1,117,265. Fuelling reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. 21 Sept., 1966 [8 Oct., 1965 (2)], No. 42168/66. Heading G6C. An installation for charging the core 10 of a liquid sodium cooled reactor comprises a device C for moving horizontally a fuel assembly A to a selected position beneath the core and a device B for moving the fuel assembly vertically into the core. The device C operates in the lower coolant space 14 of the pressure vessel 2 and comprises a beam 22 slidable in a duct 24 (closable by a valve 64) and connected by a vertical pivot 27 to a beam 26, the angular position of the beam 26 being determined by bevel gears 58, 60 driven by a shaft 62. A support 28 for a fuel assembly A is normally carried by the beam 26 and comprises a sleeve 29 engaging a notched track 32 on the beam. Spring biased winches 34 on the sleeve 29 support through cables 36 a stirrup 38, the weight of the fuel assembly A causing the winches to unwind the cables so that the fuel assembly has the position shown in Fig. 2. An arm 44 is vertically movable within the beam 26 by levers 46, 48 connected by rods 50 and operated through levers 52, 54 controlled by a rod 56 so that the sleeve 29 may be lifted from off the track 32. When the sleeve 29 is so lifted and the beams 22, 26 are in alignment the latter may be withdrawn into the duct 24 by a rod 78 coupled to a drive carriage 83, flanges 68 on the sleeve then overlying shoulders 66 so that on lowering the arm 44 the sleeve is supported by the shoulders and disconnected from the beam 26. Thus by further moving the beams by the carriage 83 the sleeve may be reconnected on a different part of the beam 26 corresponding to the selected part of the core 10 to be charged. When the sleeve 29 is supported on the flanges 68 a fuel assembly A may be lowered by means in a container 72 through a duct 70 into the stirrup 38; similarly, an irradiated fuel assembly may be withdrawn through the duct. When the fuel assembly has been positioned beneath a selected location in the core, the device B comprising a rod 15 is connected to a machine 16 and lowered thereby so that the rod may be coupled by a bayonet connection to the fuel assembly. The rod 15 is raised together with the fuel assembly, the upper end of the rod being locked within a tube upstanding from the top of the pressure vessel 2. The device B is described in greater detail with reference to Fig. 7 (not shown).
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR34365A FR1463906A (en) | 1965-10-08 | 1965-10-08 | Handling device for nuclear reactor |
FR34366A FR1463907A (en) | 1965-10-08 | 1965-10-08 | Vertical handling and attachment device for fuel assembly for nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1117265A true GB1117265A (en) | 1968-06-19 |
Family
ID=26166670
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB42168/66A Expired GB1117265A (en) | 1965-10-08 | 1966-09-21 | A fuel charging installation for a nuclear reactor |
Country Status (7)
Country | Link |
---|---|
BE (1) | BE686714A (en) |
CH (1) | CH464368A (en) |
DE (1) | DE1539818A1 (en) |
ES (1) | ES332090A1 (en) |
FR (2) | FR1463907A (en) |
GB (1) | GB1117265A (en) |
LU (1) | LU52116A1 (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3856621A (en) * | 1969-04-21 | 1974-12-24 | Asea Atom Ab | Blocking arrangement for mechanism for handling fuel assemblies in nuclear reactors |
EP0012551A1 (en) * | 1978-12-18 | 1980-06-25 | The Babcock & Wilcox Company | Support device for storing an article |
EP0993000A2 (en) * | 1998-10-07 | 2000-04-12 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
CN107767967A (en) * | 2017-09-29 | 2018-03-06 | 中广核研究院有限公司 | Fuel assembly lower locking mechanism and locking, unlocking method |
US10490311B2 (en) | 2011-08-19 | 2019-11-26 | Bwxt Mpower, Inc. | Nuclear reactor refueling methods and apparatuses |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113380430A (en) * | 2021-06-03 | 2021-09-10 | 哈尔滨工程大学 | Hydrogen recombiner catalyst loading box |
-
1965
- 1965-10-08 FR FR34366A patent/FR1463907A/en not_active Expired
- 1965-10-08 FR FR34365A patent/FR1463906A/en not_active Expired
-
1966
- 1966-09-09 BE BE686714A patent/BE686714A/xx unknown
- 1966-09-21 GB GB42168/66A patent/GB1117265A/en not_active Expired
- 1966-10-06 LU LU52116D patent/LU52116A1/xx unknown
- 1966-10-07 CH CH1449666A patent/CH464368A/en unknown
- 1966-10-07 DE DE19661539818 patent/DE1539818A1/en active Pending
- 1966-10-08 ES ES332090A patent/ES332090A1/en not_active Expired
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3856621A (en) * | 1969-04-21 | 1974-12-24 | Asea Atom Ab | Blocking arrangement for mechanism for handling fuel assemblies in nuclear reactors |
EP0012551A1 (en) * | 1978-12-18 | 1980-06-25 | The Babcock & Wilcox Company | Support device for storing an article |
EP0993000A2 (en) * | 1998-10-07 | 2000-04-12 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
EP0993000A3 (en) * | 1998-10-07 | 2000-12-13 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
US10490311B2 (en) | 2011-08-19 | 2019-11-26 | Bwxt Mpower, Inc. | Nuclear reactor refueling methods and apparatuses |
US10878970B2 (en) * | 2011-08-19 | 2020-12-29 | Bwxt Mpower, Inc. | Nuclear reactor refueling methods and apparatuses |
US11887739B2 (en) | 2011-08-19 | 2024-01-30 | Bwxt Mpower, Inc. | Nuclear reactor refueling methods and apparatuses |
CN107767967A (en) * | 2017-09-29 | 2018-03-06 | 中广核研究院有限公司 | Fuel assembly lower locking mechanism and locking, unlocking method |
CN107767967B (en) * | 2017-09-29 | 2019-10-08 | 中广核研究院有限公司 | Fuel assembly lower locking mechanism and locking, unlocking method |
Also Published As
Publication number | Publication date |
---|---|
DE1539818A1 (en) | 1970-07-16 |
FR1463907A (en) | 1966-07-22 |
BE686714A (en) | 1967-02-15 |
ES332090A1 (en) | 1969-05-16 |
LU52116A1 (en) | 1966-12-08 |
FR1463906A (en) | 1966-07-22 |
CH464368A (en) | 1968-10-31 |
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