GB935464A - Improvements in or relating to heat transfer arrangements - Google Patents
Improvements in or relating to heat transfer arrangementsInfo
- Publication number
- GB935464A GB935464A GB22043/61A GB2204361A GB935464A GB 935464 A GB935464 A GB 935464A GB 22043/61 A GB22043/61 A GB 22043/61A GB 2204361 A GB2204361 A GB 2204361A GB 935464 A GB935464 A GB 935464A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fins
- splitters
- passages
- coolant flow
- helical
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
935,464. Nuclear fuel elements. GENERAL ELECTRIC CO. Ltd. June 4, 1962 [June 19, 1961], No. 22043/61. Class 39 (4). [Also in Group XIII] A protective can for a nuclear fuel element has longitudinal fins or splitters 6 radiating from its surface to define separate flow passages A, B, C and D for the throughflow of cooling fluid, heat-exchange fins 5 also radiating from the surface of the can but to a distance less than that of the splitters 6 and being inclined to the general direction of coolant flow through the passages, partition plates 7 extending longitudinally of the passages and lying in a cylindrical surface defined by the tips of the fins 5, the plates 7 being spaced from the splitters 6 to provide openings 8 through which cooling fluid can pass to and from the fins 5, and baffle members 9 extending transversely between and radially as far as the splitters 6, the members 9 being inclined to the general direction of coolant flow through the passages at an angle equal, but of opposite sign, to the angle of inclination of the fins 5. The fins 5 may be formed integrally with the can and extend as helical members longitudinally of the can or be of herring-bone formation so that the fins in adjacent passages are inclined in opposite directions. The cooling fluid is caused to follow a plurality of paths in which it flows alternately between the fins 5 on one side of a partition plate 7 and between the baffle members 9 on the other side, undergoing a change in direction as it impinges upon the splitters 6. In order to minimize the overall impedance to coolant flow, the areas of the openings 8 should preferably equal the crosssectional areas of flow on both sides of the partition plates 7. The splitters 6 referred to above are straight but in certain arrangements it may be advantageous for them to be helical, in which ease the fins 5 may be straight, annular or helical and positioned so that they are inclined to the general direction of coolant flow through the resulting helically extending passages.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB22043/61A GB935464A (en) | 1961-06-19 | 1961-06-19 | Improvements in or relating to heat transfer arrangements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB22043/61A GB935464A (en) | 1961-06-19 | 1961-06-19 | Improvements in or relating to heat transfer arrangements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB935464A true GB935464A (en) | 1963-08-28 |
Family
ID=10172953
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB22043/61A Expired GB935464A (en) | 1961-06-19 | 1961-06-19 | Improvements in or relating to heat transfer arrangements |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB935464A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6644915B2 (en) * | 2001-03-12 | 2003-11-11 | Jeumont S.A. | Nuclear power station primary pump |
-
1961
- 1961-06-19 GB GB22043/61A patent/GB935464A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6644915B2 (en) * | 2001-03-12 | 2003-11-11 | Jeumont S.A. | Nuclear power station primary pump |
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