GB1221020A - Nuclear reactor fuel charge-discharge installation - Google Patents
Nuclear reactor fuel charge-discharge installationInfo
- Publication number
- GB1221020A GB1221020A GB07267/68A GB1726768A GB1221020A GB 1221020 A GB1221020 A GB 1221020A GB 07267/68 A GB07267/68 A GB 07267/68A GB 1726768 A GB1726768 A GB 1726768A GB 1221020 A GB1221020 A GB 1221020A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tube
- thimble
- lock
- pit
- winch
- 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
- 238000009434 installation Methods 0.000 title 1
- 239000003758 nuclear fuel Substances 0.000 title 1
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 abstract 2
- 239000000446 fuel Substances 0.000 abstract 2
- 239000002826 coolant Substances 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
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
-
- 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
- G21C19/18—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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1,221,020. Fuelling reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. 10 April, 1968 [21 April, 1967], No. 17267/68. Heading G6C. A heavy water moderated gas-cooled reactor core 12 is refuelled through channels 13 extending through a slab 19 into a space 18 provided in the pressure vessel 10. The refuelling is performed by a handling facility A described in Specification 1,219,795 which may place a number of spent fuel elements end-to-end in a thimble (Fig. 4, not shown) secured by a lock to the upper end of a pit 20. There are a number of pits 20 but only one is shown, and in alignment with each pit is a passage 30 extending through the roof of the pressure vessel to a metal dome 32 enclosing a winch (Fig. 2, not shown). An extension 48 of the pit leads to a lock 54 controlled by valves 60, 61, the thimble being unlocked and then lowered by a grab controlled by the winch into the lock where it is again locked. Whilst the thimble is in the pit 20, extension 48 and lock 54 it is cooled by the reactor coolant gas. For emergency use, the lock is surrounded by a box 58 through which water may be circulated. The thimble, after unlocking and opening of valve 61 is lowered by a tappet 78 into a magazine tube 72, the magazine then being rotated so that tube 72 lies beneath guide tube 71. A grab operated by a winch 82 lifts the fuel elements one-by-one from the thimble and places each element in a tube 84 leading to a storage pool 86. New fuel elements on a carriage 88 are introduced by lowering them by a gantry 90 through a tube 92 into a magazine tube.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR103795A FR1527225A (en) | 1967-04-21 | 1967-04-21 | Nuclear reactor fuel loading and unloading facility |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1221020A true GB1221020A (en) | 1971-02-03 |
Family
ID=8629448
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB07267/68A Expired GB1221020A (en) | 1967-04-21 | 1968-04-10 | Nuclear reactor fuel charge-discharge installation |
Country Status (6)
| Country | Link |
|---|---|
| BE (1) | BE713093A (en) |
| CH (1) | CH489094A (en) |
| ES (1) | ES352674A1 (en) |
| FR (1) | FR1527225A (en) |
| GB (1) | GB1221020A (en) |
| LU (1) | LU55856A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2300817C2 (en) * | 2005-06-30 | 2007-06-10 | ФГУП Опытное конструкторское бюро "ГИДРОПРЕСС" | Nuclear steam-generating plant |
| RU2393562C1 (en) * | 2009-02-16 | 2010-06-27 | Федеральное государственное унитарное предприятие "Всероссийский Электротехнический институт им. В.И. Ленина" (ФГУП ВЭИ) | Undeground nuclear heat power plant of vertical shaft design |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2154363B2 (en) * | 1971-11-02 | 1979-01-11 | Kraftwerk Union Ag, 4330 Muelheim | Straight through filter |
| 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 |
| FR2445589A1 (en) * | 1978-12-29 | 1980-07-25 | Commissariat Energie Atomique | Transfer container for radioactive nuclear fuel elements - comprises finned double-walled cylindrical vessel with cooling water circulation, ensuring cooling of element in all circumstances |
| FR2486297A1 (en) * | 1980-07-01 | 1982-01-08 | Novatome | DEVICE FOR LOADING AND UNLOADING COMBUSTIBLE ASSEMBLIES FOR FAST NEUTRON NUCLEAR REACTOR |
| GB2588842A (en) * | 2020-07-23 | 2021-05-12 | Rolls Royce Plc | Nuclear refuelling device |
-
1967
- 1967-04-21 FR FR103795A patent/FR1527225A/en not_active Expired
-
1968
- 1968-04-02 BE BE713093D patent/BE713093A/xx unknown
- 1968-04-04 CH CH499068A patent/CH489094A/en not_active IP Right Cessation
- 1968-04-08 LU LU55856D patent/LU55856A1/xx unknown
- 1968-04-10 GB GB07267/68A patent/GB1221020A/en not_active Expired
- 1968-04-11 ES ES352674A patent/ES352674A1/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2300817C2 (en) * | 2005-06-30 | 2007-06-10 | ФГУП Опытное конструкторское бюро "ГИДРОПРЕСС" | Nuclear steam-generating plant |
| RU2393562C1 (en) * | 2009-02-16 | 2010-06-27 | Федеральное государственное унитарное предприятие "Всероссийский Электротехнический институт им. В.И. Ленина" (ФГУП ВЭИ) | Undeground nuclear heat power plant of vertical shaft design |
Also Published As
| Publication number | Publication date |
|---|---|
| LU55856A1 (en) | 1968-07-03 |
| CH489094A (en) | 1970-04-15 |
| FR1527225A (en) | 1968-05-31 |
| ES352674A1 (en) | 1970-10-16 |
| BE713093A (en) | 1968-08-16 |
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