GB836562A - Improvements in nuclear reactor fuel element handling plant - Google Patents
Improvements in nuclear reactor fuel element handling plantInfo
- Publication number
- GB836562A GB836562A GB12127/56A GB1212756A GB836562A GB 836562 A GB836562 A GB 836562A GB 12127/56 A GB12127/56 A GB 12127/56A GB 1212756 A GB1212756 A GB 1212756A GB 836562 A GB836562 A GB 836562A
- Authority
- GB
- United Kingdom
- Prior art keywords
- shoot
- sections
- fuel element
- shoots
- chamber
- 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 1
- 239000000446 fuel Substances 0.000 abstract 4
- 229910001018 Cast iron Inorganic materials 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- 229910000831 Steel Inorganic materials 0.000 abstract 1
- 239000004411 aluminium Substances 0.000 abstract 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract 1
- 229910052782 aluminium Inorganic materials 0.000 abstract 1
- 238000007599 discharging Methods 0.000 abstract 1
- 239000000463 material Substances 0.000 abstract 1
- 230000002285 radioactive effect Effects 0.000 abstract 1
- 239000010959 steel Substances 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
- G21C19/32—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)
- Chutes (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Control And Safety Of Cranes (AREA)
Abstract
836,562. Handling materials in radioactive environment. BABCOCK & WILCOX Ltd. April 18, 1957 [April 20, 1956], No. 12127/56. Class 39(4). [Also in Group XXX] Spent rod-like fuel elements are transferred from the top 3 of a concrete reactor housing 2 to a pond 90 by a helical shoot 12X or 12Y into either one of which a fuel element may be dropped from a loading machine 5. The machine 5 is movable on railway tracks 4 to the various element-collections on the top 3 and the filled machine is brought to a desired one of a pair of discharging positions corresponding to the entrances to the shoots. The lower end 12DX of the shoots lie spaced from each other in the same horizontal, or substantially horizontal plane, Fig. 2 (not shown), and each shoot terminates in a discharge chamber 13X. Frictional forces brake the descent of a fuel element so that it would come to rest within the end 12DX; however, the element is driven into the chamber 13X by water jets 48, 49 arranged in upper surface of the shoot. The elements are removed from the discharge chambers in a skip 103 on a hoist carriage 102 running on inclined tracks 101, a transporter crane 120 moving a skip from its carriage to a desired part of the pond 90. Each discharge chamber has its own hoist carriage and the arrangement is as described in Specification 808,381 (see Group XL(a)). The shoots are formed of cast iron twelve inches thick for biological protection and the helical parts are divided into sections about five feet six inches long each section having a thick lid 19. The sections are secured end to end by bolts in lugs 22 and the spaces therebetween caulked with lead and aluminium. Each section may be removed and lifted upwards within the chamber 18 without disturbing adjacent sections and to this end the junctions between adjacent sections are each supported on a single cradle 27 carried by a steel framework 25, 26, Fig. 5 (not shown). Should fuel element prematurely come to rest within the helical part of a shoot it may be dislodged by high pressure water jets provided in alternate shoot sections ; alternatively, cast iron plugs 36 may be removed and pole rods inserted in the holes 35.
Priority Applications (9)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB4453/56A GB808381A (en) | 1956-04-20 | 1956-02-13 | Improvements in nuclear reactor fuel element handling plant |
| GB12127/56A GB836562A (en) | 1956-04-20 | 1956-04-20 | Improvements in nuclear reactor fuel element handling plant |
| GB24802/56A GB836563A (en) | 1956-02-13 | 1956-08-14 | Improvements in material handling plant, more particularly plant for handling nuclear reactor fuel elements |
| US639539A US2995504A (en) | 1956-02-13 | 1957-02-11 | Material handling plant |
| DEB43476A DE1036409B (en) | 1956-02-13 | 1957-02-12 | Transport system for fuel elements of a nuclear reactor |
| FR1179265D FR1179265A (en) | 1956-02-13 | 1957-02-13 | Conveyor for fuel elements removed from a nuclear reactor |
| BE554973D BE554973A (en) | 1956-02-13 | 1957-02-13 | |
| FR1179310D FR1179310A (en) | 1956-02-13 | 1957-04-20 | Improvements to facilities for handling materials and in particular the fuel elements of a nuclear reactor |
| BE556886D BE556886A (en) | 1956-02-13 | 1957-04-20 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB12127/56A GB836562A (en) | 1956-04-20 | 1956-04-20 | Improvements in nuclear reactor fuel element handling plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB836562A true GB836562A (en) | 1960-06-01 |
Family
ID=9998856
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4453/56A Expired GB808381A (en) | 1956-02-13 | 1956-02-13 | Improvements in nuclear reactor fuel element handling plant |
| GB12127/56A Expired GB836562A (en) | 1956-02-13 | 1956-04-20 | Improvements in nuclear reactor fuel element handling plant |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4453/56A Expired GB808381A (en) | 1956-02-13 | 1956-02-13 | Improvements in nuclear reactor fuel element handling plant |
Country Status (1)
| Country | Link |
|---|---|
| GB (2) | GB808381A (en) |
-
1956
- 1956-02-13 GB GB4453/56A patent/GB808381A/en not_active Expired
- 1956-04-20 GB GB12127/56A patent/GB836562A/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| GB808381A (en) | 1959-02-04 |
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