GB855661A - Improvements in or relating to protective cans for nuclear reactor fuel elements - Google Patents
Improvements in or relating to protective cans for nuclear reactor fuel elementsInfo
- Publication number
- GB855661A GB855661A GB11950/57A GB1195057A GB855661A GB 855661 A GB855661 A GB 855661A GB 11950/57 A GB11950/57 A GB 11950/57A GB 1195057 A GB1195057 A GB 1195057A GB 855661 A GB855661 A GB 855661A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fins
- baffles
- length
- along
- nuclear reactor
- 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
855,661. Nuclear reactors. GENERAL ELECTRIC CO. Ltd. April 10, 1958 [April 11, 1957], No. 11950/57. Class 39(4). A protective can for a nuclear reactor fuel element is provided with a plurality of longitudinal fins radiating from the outside of the main body of the can, passages being arranged through the fins at intervals along their lengths, and with baffles between adjacent fins, the baffles extending along a part or the whole of the length of the fins and each varying in distance from the main body along its length from a maximum at one end of the baffle to a minimum at the other. The can shown in Fig. 3 comprises a cylindrical body 1 provided with longitudinal fins 2. Between each pair of adjacent fins extend planar baffles which run along the whole length of the fins. Baffles 4 are fixed between the tips of the fins at their lower ends and near the roots of the fins at their upper ends ; baffles 5 are secured near the roots of the fins at their lower ends and near the tips of the fins at their upper ends. The fins are provided with radial slots 6 which may be arranged to lie on a continuous spiral or may be arranged in a series of planes transverse to the axis. The baffles need not be the same length as the fins ; baffles of a half, a third, or a quarter of the length may be employed, arranged in series along the length of the space between the fins and arranged to have similar or alternate inclinations. Specification 791,011 is referred to.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB11950/57A GB855661A (en) | 1957-04-11 | 1957-04-11 | Improvements in or relating to protective cans for nuclear reactor fuel elements |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB11950/57A GB855661A (en) | 1957-04-11 | 1957-04-11 | Improvements in or relating to protective cans for nuclear reactor fuel elements |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB855661A true GB855661A (en) | 1960-12-07 |
Family
ID=9995617
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB11950/57A Expired GB855661A (en) | 1957-04-11 | 1957-04-11 | Improvements in or relating to protective cans for nuclear reactor fuel elements |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB855661A (en) |
-
1957
- 1957-04-11 GB GB11950/57A patent/GB855661A/en not_active Expired
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| ES8105881A1 (en) | Fuel assembly for a boiling nuclear reactor | |
| GB873073A (en) | Improvements in or relating to fuel elements for nuclear reactors | |
| GB1244611A (en) | Improvements in or relating to heat exchangers | |
| US3150057A (en) | Fuel subassembly for nuclear reactor | |
| ES347974A1 (en) | Nuclear fuel assembly | |
| ES238598A1 (en) | Nuclear reactor fuel elements | |
| GB855661A (en) | Improvements in or relating to protective cans for nuclear reactor fuel elements | |
| GB942591A (en) | Improvements in or relating to fuel elements for nuclear reactors | |
| GB1088022A (en) | Nuclear fuel assemblies | |
| GB873552A (en) | Improvements in and relating to fuel elements for nuclear reactors | |
| GB917278A (en) | Improvements in or relating to heat exchangers | |
| US3049485A (en) | Support structures | |
| GB1206733A (en) | Fuel subassembly for a liquid-metal-cooled fast reactor | |
| GB1189253A (en) | Improvements in and relating to Water Separators for Saturated-Steam Generators | |
| GB1088894A (en) | Fuel rod structure | |
| ES456346A1 (en) | Tubular heat exchangers and tube bundle for use therein | |
| GB1317356A (en) | Nuclear fuel subassembly | |
| GB1207940A (en) | Nuclear fuel rod having an offset plenum | |
| GB984931A (en) | Improvements in or relating to finned tubular bodies | |
| GB879904A (en) | Improvements in or relating to supporting arrangements for nuclear reactor fuel elements | |
| GB915331A (en) | Improvements in or relating to nuclear reactors | |
| GB849157A (en) | Improvements in and relating to fuel elements for nuclear reactors | |
| REHME | Systematic experimental study of the dependence of the pressure loss on the geometrical arrangement for rod bundles with spiral wire spacers in a longitudinal flow(Systematic experimental study of effects of spiral pitch, rod spacing ratio, and number of rods in rod bundle fuel elements on pressure loss)[M. S. Thesis- Karlsruhe univ.] | |
| ES309336A1 (en) | Improvements in tubular elements for heat exchangers and particularly in sheaths for nuclear fuel | |
| GB1058577A (en) | Improvements in or relating to pressure exchanger cell rings |