GB1382797A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1382797A GB1382797A GB5140571A GB5140571A GB1382797A GB 1382797 A GB1382797 A GB 1382797A GB 5140571 A GB5140571 A GB 5140571A GB 5140571 A GB5140571 A GB 5140571A GB 1382797 A GB1382797 A GB 1382797A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sub
- transfer
- gripper
- assembly
- transfer member
- 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
- G21C19/16—Articulated or telescopic chutes or tubes for connection to channels in the reactor core
-
- 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)
- Load-Engaging Elements For Cranes (AREA)
Abstract
1382797 Refuelling reactors BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd 3 Nov 1972 [4 Nov 1971] 51405/71 Heading G6C A nuclear reactor comprises a transfer machine 20 which acts to transfer fuel-elements or other components from core-discharging apparatus to a storage facility and vice versa. The machine 20 is disposed laterally of the core 12 and has a transfer member 22 movable on a pantograph mechanism 21 between or transfer position in which it transfers a component such as a full sub-assembly 32 to or from a respective gripper 18 of a charging machine 16 or 17 (which has been appropriately positioned by rotation of closure plugs 14, 15) and a datum position beneath a gripper 23 for transferring the sub-assembly 32 from or to a careusel 24 to which access may be had, via tube 29, from the exterior of the reactor. The transfer member 22 is constructed to receive a bottom spigot 33 which normally locates the sub-assembly 32 in the core 12, and provides a pad 42 to support the sub-assembly 32 at a slight inclination. The transfer member may be arranged to support two sub-assemblies 32 simultaneously (Fig. 4, not shown) to speed up the refuelling operation by reducing the member of transfer movements. The charging machines 16, 17 may be rotatable relative to the closure plug 15 and may include means to hold down core components adjacent the one being removed. In modifications (Figs. 6 and 7, not shown), the gripper 18 and the transfer member 22 are constructed to provide interference members which coact to prevent, respectively, release of a sub-assembly 32, whose spigot 33 is damaged or missing, from the gripper 18 to the transfer member 22, and movement of the transfer member 22 away from the transfer position until the gripper 18 is fully clear of a fuel subassembly. In the core 12, the sub-assemblies 32 may be disposed at a slight angle to the vertical and supported by leaning posts so as to reduce their vibration due to flow of the sodium coolant.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5140571A GB1382797A (en) | 1971-11-04 | 1971-11-04 | Nuclear reactors |
FR7238965A FR2158491B1 (en) | 1971-11-04 | 1972-11-03 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5140571A GB1382797A (en) | 1971-11-04 | 1971-11-04 | Nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1382797A true GB1382797A (en) | 1975-02-05 |
Family
ID=10459883
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB5140571A Expired GB1382797A (en) | 1971-11-04 | 1971-11-04 | Nuclear reactors |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR2158491B1 (en) |
GB (1) | GB1382797A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4961899A (en) * | 1984-08-23 | 1990-10-09 | Westinghouse Electric Corp. | Multiple-cable connecting device for a nuclear reactor |
WO2011067230A1 (en) | 2009-12-02 | 2011-06-09 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Device and method assisting the loading and unloading of the core of a nuclear reactor and sodium-cooled nuclear reactor including such a device |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4069098A (en) * | 1976-02-23 | 1978-01-17 | Westinghouse Electric Corporation | Ex-vessel nuclear fuel transfer system |
US5019327A (en) * | 1990-01-25 | 1991-05-28 | General Electric Company | Fuel assembly transfer basket for pool type nuclear reactor vessels |
FR3019931B1 (en) * | 2014-04-11 | 2016-05-13 | Commissariat Energie Atomique | UNIT FOR LOADING / UNLOADING COMBUSTIBLE ASSEMBLIES OF A METALLIQUID COOLED REACTOR, SUCH AS A RNR-NA OR SFR REACTOR, INCORPORATING A DEVICE FOR MEASURING THE RESIDUAL POWER |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE573083A (en) * | 1957-11-18 |
-
1971
- 1971-11-04 GB GB5140571A patent/GB1382797A/en not_active Expired
-
1972
- 1972-11-03 FR FR7238965A patent/FR2158491B1/fr not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4961899A (en) * | 1984-08-23 | 1990-10-09 | Westinghouse Electric Corp. | Multiple-cable connecting device for a nuclear reactor |
WO2011067230A1 (en) | 2009-12-02 | 2011-06-09 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Device and method assisting the loading and unloading of the core of a nuclear reactor and sodium-cooled nuclear reactor including such a device |
Also Published As
Publication number | Publication date |
---|---|
FR2158491B1 (en) | 1978-03-03 |
FR2158491A1 (en) | 1973-06-15 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |