GB897449A - Improvements in or relating to refuelling machines for nuclear reactors - Google Patents
Improvements in or relating to refuelling machines for nuclear reactorsInfo
- Publication number
- GB897449A GB897449A GB3291/59A GB329159A GB897449A GB 897449 A GB897449 A GB 897449A GB 3291/59 A GB3291/59 A GB 3291/59A GB 329159 A GB329159 A GB 329159A GB 897449 A GB897449 A GB 897449A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tube
- reactor
- plug
- standpipe
- magazine
- 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
- G21C19/22—Arrangements for obtaining access to the interior of a pressure vessel whilst the reactor is operating
-
- 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
-
- 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)
Abstract
897,449. Handling nuclear fuel elements. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Jan. 22, 1960 [Jan. 29, 1959; June 3, 1959], Nos. 3291/59 and 18956/59. Class 39(4). A reactor refuelling machine has incorporated in it adjacent to its normal refuelling equipment, separate equipment for use in conditions in which the normal equipment cannot be used, the separate equipment being similar to the normal equipment but modified to adapt it for use in the said conditions, whereby the separate equipment can be brought rapidly into operative position by moving the machine by a small amount. A typical condition in which the separate equipment would be used is the removal of a damaged fuel element from a reactor channel. As shown in Figs. 1a-1c (which are superimposed to form a single Fig. 1) the machine 1 has facilities for normal refuelling including a pressure vessel 2, a retractable nose piece 3 for sealing engagement with a selected reactor standpipe 4 and a rotatable fuel element magazine 5 having three tubes 6 alignable in turn with the nose piece, each tube having its own hoisting chain 7 driven by a common hoisting means 8. A seal plug 33 and telescopic connecting means 34 are attached to each chain 7. The separate equipment for use in abnormal conditions comprises a pressure vessel 9 housing a fuel element magazine 10 containing three tubes 11, the tubes being alignable in turn with a retractable nose piece 12. The tubes 11 may also be aligned with an outlet tube 13 having an isolating valve 14, a movable shield 15 and an access door 16. A grab 17 and shield plug 18 are suspended in the tube 13 from a cable 19 driven by a winch 20. One of the tubes 11 contains a dump can for receiving fuel element fragments. The reactor charge face comprises standpipe caps 21 and after removal of the selected cap the machine 1 is positioned thereover. The machine has fixed shielding 22 and removable shielding 23 to give access to a space 25 accommodating the nose pieces 3, 12. A tube 26 between the magazine 5 and nose piece 3 has a window 27 observed by a television camera 28, and a tube 29 between the magazine 10 and nose piece 12 has a window 30 for a television camera 31. To refuel a reactor an assembly consisting of a string of fuel elements suspended from a shielding plug 36 for a standpipe 4 is loaded into one of the magazine tubes 6 and another tube 6 is loaded with a spare plug 36. The shielding 23 is removed and the chain 7 of the empty tube 6 is lowered through the tube 26 until the plug 33 reaches its sealing position (Fig. 1a), the connecting means 34 being extended to connect with the standpipe plug 36. The shielding 23 is replaced and the nose piece 3 lowered to seal with the standpipe, coolant as used in the reactor and at the same pressure then being circulated through the vessel 2. The hoist 8 lifts the plug 36 together with its connected string of fuel elements into the empty tube 6. The magazine 5 is rotated so that its tube 6 loaded with the replacement fuel assembly is aligned with the standpipe and this assembly is lowered into the reactor. Should a fuel element be accidentally dropped into the reactor the spare plug 36 in the tube 6 is lowered into the standpipe and the reactor is depressurized, the nose piece 3 retracted and the connecting means 34 telescoped. The machine is moved a small amount so that the nose piece 12 may be lowered and sealed with the standpipe and the valves 14, 32 are opened. The grab 17 is lowered through an empty tube 11 and lifts the spare plug 36 into the magazine 10, the latter then being rotated to permit lowering of the grab through tubes 11, 29 to retrieve the damaged fuel element. The element is lifted into the tube 13, the magazine rotated, and the element deposited in the dump can. The vessel 9 may also be circulated with coolant. Specifications 873,073, 875,787, 889,536, 897,448, 897,450, 897,451, 897,454 and 897,458 are referred to.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3291/59A GB897449A (en) | 1959-01-29 | 1959-01-29 | Improvements in or relating to refuelling machines for nuclear reactors |
FR816986A FR1247089A (en) | 1959-01-29 | 1960-01-28 | Nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3291/59A GB897449A (en) | 1959-01-29 | 1959-01-29 | Improvements in or relating to refuelling machines for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB897449A true GB897449A (en) | 1962-05-30 |
Family
ID=9755547
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3291/59A Expired GB897449A (en) | 1959-01-29 | 1959-01-29 | Improvements in or relating to refuelling machines for nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB897449A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2150342A (en) * | 1983-11-21 | 1985-06-26 | Westinghouse Electric Corp | Refueling machine mounted fuel assembly inspection t.v. cameras |
CN103400618A (en) * | 2013-07-01 | 2013-11-20 | 中国核电工程有限公司 | Core asymmetric loading method for VVER nuclear power station reactor |
-
1959
- 1959-01-29 GB GB3291/59A patent/GB897449A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2150342A (en) * | 1983-11-21 | 1985-06-26 | Westinghouse Electric Corp | Refueling machine mounted fuel assembly inspection t.v. cameras |
US4643867A (en) * | 1983-11-21 | 1987-02-17 | Westinghouse Electric Corp. | Refueling machine mounted fuel assembly inspection T.V. cameras |
CN103400618A (en) * | 2013-07-01 | 2013-11-20 | 中国核电工程有限公司 | Core asymmetric loading method for VVER nuclear power station reactor |
CN103400618B (en) * | 2013-07-01 | 2016-04-20 | 中国核电工程有限公司 | The asymmetric stowage of a kind of VVER nuclear power station reactor core |
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