GB1168853A - Improvements relating to Servicing Tools for Nuclear Reactors - Google Patents
Improvements relating to Servicing Tools for Nuclear ReactorsInfo
- Publication number
- GB1168853A GB1168853A GB09094/67A GB1909467A GB1168853A GB 1168853 A GB1168853 A GB 1168853A GB 09094/67 A GB09094/67 A GB 09094/67A GB 1909467 A GB1909467 A GB 1909467A GB 1168853 A GB1168853 A GB 1168853A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tool
- sleeve
- clasp
- tie rod
- rod
- 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
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
- G21C19/36—Mechanical means only
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23D—PLANING; SLOTTING; SHEARING; BROACHING; SAWING; FILING; SCRAPING; LIKE OPERATIONS FOR WORKING METAL BY REMOVING MATERIAL, NOT OTHERWISE PROVIDED FOR
- B23D23/00—Machines or devices for shearing or cutting profiled stock
- B23D23/04—Machines or devices for shearing or cutting profiled stock by means of holding-dies, arranged side by side, subjecting the stock to torsional stress
-
- 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
- G21C19/207—Assembling, maintenance or repair of reactor components
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Working Measures On Existing Buildindgs (AREA)
Abstract
1,168,853. Bending; breaking. FAIREY ENG. Ltd. 24 July, 1968 [25 April, 1967], No. 19094/67. Heading B3E. A parting tool for breaking a rod by repeatedly-reversed bending, for example the tie rods of fuel stringers in a nuclear reactor, comprises a pair of clasp members adapted to grip adjacent lengths of the rod, and means for angularly oscillating one clasp member relatively to the other about an axis passing transversely to the length of the rod and between the clasp members. The tool is mounted on a base 10 slidable on a fixed bed 12 located above a disposal vault for active waste the entry port 13 of which is closed by a shield plug 14. The tool frame 15 carries a front guide tube 17, a seal plug retraction cylinder 18 and a two-part articulated clasp sleeve assembly 19. The clasp assembly comprises an upper non-pivoting sleeve 21 and a lower pivoting sleeve 24 each provided with clamping jaws 31 actuated hydraulically or pneumatically by rams 32 and 33 respectively. A tie rod to be broken passes through the aligned sleeves and clamps and rests on a retractible rod stop 50 positioned over the entry port 13. The lower sleeve is oscillated by a hydraulic or pneumatic cylinder 42 mounted on a lead screw 45. In the event of failure of the cylinder 42 the sleeve may be brought to a vertical position manually or by a motor through a transmission 47. A leadscrew mechanism 60 is provided for moving the tool along the bed 12 and a manual transmission 64 is provided for emergency use. In operation, the retraction cylinder 18 is energized to withdraw the shield plug 14 into a guide sleeve 75. The tool is moved horizontally by the leadscrew 60 until the clasp sleeve assembly 19 is located above the entry port 13. With the clamps open a tie rod is lowered by a hoist (not shown) until its end rests on the stop 50. The clamps are closed and the cylinder 42 actuated to oscillate the lower clasp sleeve. On breakage of the tie rod the oscillation is stopped, the stop 50 is retracted and the lower clamp 30 opened to allow the parted lower part of the tie rod to fall into the vault. The stop 50 is advanced to cover the entry port and the upper clamp 30 is opened to allow the remainder of the tie rod to be lowered on to the stop in readiness for a further cycle of operations. The tie rod may be released from the lower clamp by a latch 80 in the event of seizure of the lower clamp cylinder 33. The front guide tube 17 is used as a bypass for a fuel tie rod on failure of the breaking tool or in an emergency. The tool is provided with limit switches connected to an indicator circuit which indicates the positions and operation of the various parts of the tool.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB09094/67A GB1168853A (en) | 1967-04-25 | 1967-04-25 | Improvements relating to Servicing Tools for Nuclear Reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB09094/67A GB1168853A (en) | 1967-04-25 | 1967-04-25 | Improvements relating to Servicing Tools for Nuclear Reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1168853A true GB1168853A (en) | 1969-10-29 |
Family
ID=10123689
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB09094/67A Expired GB1168853A (en) | 1967-04-25 | 1967-04-25 | Improvements relating to Servicing Tools for Nuclear Reactors |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB1168853A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5216471U (en) * | 1975-07-25 | 1977-02-05 | ||
| FR2472250A1 (en) * | 1979-12-20 | 1981-06-26 | Nukem Gmbh | METHOD AND APPARATUS FOR EXTINGUISHING NUCLEAR COMBUSTIBLE MATERIALS FROM THEIR SOLDERING TUBES |
| EP0106633A1 (en) * | 1982-10-11 | 1984-04-25 | United Kingdom Atomic Energy Authority | Machine and method for rendering irradiated nuclear fuel pins into short lengths |
-
1967
- 1967-04-25 GB GB09094/67A patent/GB1168853A/en not_active Expired
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5216471U (en) * | 1975-07-25 | 1977-02-05 | ||
| FR2472250A1 (en) * | 1979-12-20 | 1981-06-26 | Nukem Gmbh | METHOD AND APPARATUS FOR EXTINGUISHING NUCLEAR COMBUSTIBLE MATERIALS FROM THEIR SOLDERING TUBES |
| EP0106633A1 (en) * | 1982-10-11 | 1984-04-25 | United Kingdom Atomic Energy Authority | Machine and method for rendering irradiated nuclear fuel pins into short lengths |
| US4580708A (en) * | 1982-10-11 | 1986-04-08 | United Kingdom Atomic Energy Authority | Machine and method for rendering irradiated nuclear fuel pins into short lengths |
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