GB857422A - Improvements in or relating to support means for a nuclear reactor fuel element - Google Patents
Improvements in or relating to support means for a nuclear reactor fuel elementInfo
- Publication number
- GB857422A GB857422A GB36737/57A GB3673757A GB857422A GB 857422 A GB857422 A GB 857422A GB 36737/57 A GB36737/57 A GB 36737/57A GB 3673757 A GB3673757 A GB 3673757A GB 857422 A GB857422 A GB 857422A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sleeve
- fuel element
- fins
- spigot
- nov
- 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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/38—Fuel units consisting of a single fuel element in a supporting sleeve or in another supporting element
-
- 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)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
857,422. Nuclear fuel elements. GENERAL ELECTRIC CO. Ltd. Nov. 25, 1958 [Nov. 25, 1957], No. 36737/57. Class 39(4). A rod type fuel element 1 enclosed in a can 2 having fins 14, Fig. 1, is supported in a graphite sleeve 5 by a beam 6, the assembly being removable as a unit from a channel within the reactor core. The beam 6 is preferably of a sintered alumina based ceramic material, but alternatively may be of graphite or metal, and has an opening 11 receiving a spigot 3 on the fuel element end cap 15, a circular channel 12 in the beam receiving an extension of the can and end cap. The beam 6 is introduced into the sleeve 5 in the chain-line position 9 and is then orientated to lie on the lower edges of slots 7, 8, the longer slot 7 permitting this turning movement, the spigot 3 then being introduced into the opening 11 and retained by a disc 13. In a modified arrangement, Figs. 4, 6, the can 2 has straight longitudinal fins 16 and four helical fins 17 closely approaching the inner wall of the sleeve 5. The fuel element 1 is supported by the beam 6 but is centralised within the sleeve by spiders 19, 21 secured to the upper and lower ends of the can, the ends of the fins 17 being attached to the spider arms. Specification 791,011 is referred to.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB36737/57A GB857422A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to support means for a nuclear reactor fuel element |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB36737/57A GB857422A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to support means for a nuclear reactor fuel element |
Publications (1)
Publication Number | Publication Date |
---|---|
GB857422A true GB857422A (en) | 1960-12-29 |
Family
ID=10390796
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB36737/57A Expired GB857422A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to support means for a nuclear reactor fuel element |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB857422A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1234334B (en) * | 1961-05-10 | 1967-02-16 | Babcock & Wilcox Dampfkessel | Support grid for nuclear reactor fuel elements |
DE1244304B (en) * | 1962-02-15 | 1967-07-13 | Atomic Energy Authority Uk | Support device for stacked nuclear reactor fuel elements |
CN113362972A (en) * | 2021-06-04 | 2021-09-07 | 中国核动力研究设计院 | Fuel rod positioning structure and fuel assembly for overcoming field force repulsion of fuel rod abrasion |
-
1957
- 1957-11-25 GB GB36737/57A patent/GB857422A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1234334B (en) * | 1961-05-10 | 1967-02-16 | Babcock & Wilcox Dampfkessel | Support grid for nuclear reactor fuel elements |
DE1244304B (en) * | 1962-02-15 | 1967-07-13 | Atomic Energy Authority Uk | Support device for stacked nuclear reactor fuel elements |
CN113362972A (en) * | 2021-06-04 | 2021-09-07 | 中国核动力研究设计院 | Fuel rod positioning structure and fuel assembly for overcoming field force repulsion of fuel rod abrasion |
CN113362972B (en) * | 2021-06-04 | 2022-04-29 | 中国核动力研究设计院 | Fuel rod positioning structure and fuel assembly for overcoming field force repulsion of fuel rod abrasion |
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