GB814996A - Improvements in or relating to apparatus for handling nuclear reactor fuel elements - Google Patents
Improvements in or relating to apparatus for handling nuclear reactor fuel elementsInfo
- Publication number
- GB814996A GB814996A GB25613/56A GB2561356A GB814996A GB 814996 A GB814996 A GB 814996A GB 25613/56 A GB25613/56 A GB 25613/56A GB 2561356 A GB2561356 A GB 2561356A GB 814996 A GB814996 A GB 814996A
- Authority
- GB
- United Kingdom
- Prior art keywords
- centre
- die
- rod
- crosshead
- fuel
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 239000000446 fuel Substances 0.000 abstract 3
- 210000002832 Shoulder Anatomy 0.000 abstract 1
- 229910052782 aluminium Inorganic materials 0.000 abstract 1
- 239000004411 aluminium Substances 0.000 abstract 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminum Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract 1
- VYZAMTAEIAYCRO-UHFFFAOYSA-N chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 abstract 1
- 229910052804 chromium Inorganic materials 0.000 abstract 1
- 239000011651 chromium Substances 0.000 abstract 1
- 238000005260 corrosion Methods 0.000 abstract 1
- 238000000605 extraction Methods 0.000 abstract 1
- 239000012530 fluid Substances 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 230000000284 resting Effects 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
- 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
-
- 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)
- Perforating, Stamping-Out Or Severing By Means Other Than Cutting (AREA)
Abstract
814,996. Broaching; breaking. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. July 22, 1957 [Aug. 22, 1956], No. 25613/56. Classes 83 (3) and 83 (4). Apparatus for cutting away the sheath 28 from a nuclear-reactor fuel element comprises an annular cutting die 11 and means 70 for preventing bowing of the element as it is passed through the die. The element is initially supported by V-guides 21 which are raised by a rod 64 engaging a lever 63. When a crosshead 31 is advanced by a fluid-pressure ram 43, it moves a centre 30 up to one end of the element and moves the other end of the element against a spring-pressed recessed centre 29 which projects through the fixed die 11. The bowpreventing rollers 70 are then forced against the sheath by fluid pressure means 69, and the V-guides 21 are withdrawn. As the ram 43 advances further, the cross-head 31 engages shoulders 38 on rods 19 connected to a crosshead 36 carrying the centre 29, and the crossheads 31, 36 advance together with the element. When the end cap 33 has been sheared through, the rollers 70 are withdrawn and the element passes completely through the die. At the end of its stroke the cross-head 36 breaks into four pieces a previously stripped fuel-rod, resting in slots 62 in the machine frame, by projections 55 co-operating with a fixed abutment 60. Prior to this, a fixed cam strikes a lever engaging a slot 53 in the centre 29, thus releasing the fuel rod. When the cross-head 31 is returned, the last part of its movement causes the centre 30 to be drawn through a stripper crosshead 45 to remove the cut cap 35. The fuel rod is picked up with tongs and placed in the slots 62 for breaking. The broken fuel rod is removed to an extraction plant. The whole process is carried out under water, and the machine parts are chromium plated or aluminium sprayed to prevent corrosion.
Priority Applications (7)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| BE560240D BE560240A (en) | 1956-08-22 | ||
| NL220092D NL220092A (en) | 1956-08-22 | ||
| NL106521D NL106521C (en) | 1956-08-22 | ||
| US675201A US2978790A (en) | 1956-08-22 | 1957-07-30 | Apparatus for handling nuclear reactor fuel elements |
| DEU4707A DE1042777B (en) | 1956-08-22 | 1957-08-06 | Apparatus for treating nuclear reactor fuel elements |
| FR1181175D FR1181175A (en) | 1956-08-22 | 1957-08-13 | Apparatus for handling nuclear reactor fuel elements |
| CH355227D CH355227A (en) | 1956-08-22 | 1957-08-20 | Device for removing the protective covering from fuel elements for nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB814996A true GB814996A (en) | 1959-06-17 |
Family
ID=1739357
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB25613/56A Expired GB814996A (en) | 1956-08-22 | 1956-08-22 | Improvements in or relating to apparatus for handling nuclear reactor fuel elements |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB814996A (en) |
-
1956
- 1956-08-22 GB GB25613/56A patent/GB814996A/en not_active Expired
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| GB1314803A (en) | Method of and apparatus for shearing spent nuclear fuel bundles | |
| GB938521A (en) | A method for the indirect extrusion of metal and means for carrying out the method | |
| GB814996A (en) | Improvements in or relating to apparatus for handling nuclear reactor fuel elements | |
| US3173320A (en) | Machine for separating irradiated fuel slugs from their jackets | |
| US3018885A (en) | Extrusion and stretch-straightening apparatus and method | |
| GB935438A (en) | Metal extrusion press with rotary container | |
| US2978790A (en) | Apparatus for handling nuclear reactor fuel elements | |
| JPS5762814A (en) | Method and apparatus for extrusion forging | |
| US2880636A (en) | Cutting and wedging jacket remover | |
| GB1156569A (en) | Multistage press for the production of workpieces whose axial length is short as compared with their diameter | |
| GB870889A (en) | Apparatus for forming bolts, screws or rivets by hot pressing | |
| CN212760615U (en) | Punch press for parts machining | |
| SU281130A1 (en) | PRIVSS PIPELINE | |
| JPS55112146A (en) | Die forging device | |
| CN218252457U (en) | Caliper piston forming die | |
| KR890007436Y1 (en) | Round product ejecting mold device of press | |
| GB942885A (en) | Improvements in or relating to press tools | |
| GB928834A (en) | A machine for removing the cartridges of nuclear reactor fuel elements | |
| GB1180033A (en) | Improvements in Apparatus for the Removal of Sheaths from Nuclear Fuel Elements. | |
| SU122731A1 (en) | Method of hydraulic sheet punching (drawing) | |
| JPS5682126A (en) | Cutting apparatus for tube | |
| JPS5533889A (en) | Numerical control press machine provided with die operation detector | |
| GB1138662A (en) | Device for ejecting workpieces from presses | |
| JPS5550942A (en) | Forging press | |
| JPS537629A (en) | Improved method for isolating and purifying vinylphenol |