GB978375A - Improvements in pressure-fluid cooled nuclear reactors - Google Patents
Improvements in pressure-fluid cooled nuclear reactorsInfo
- Publication number
- GB978375A GB978375A GB7728/63A GB772863A GB978375A GB 978375 A GB978375 A GB 978375A GB 7728/63 A GB7728/63 A GB 7728/63A GB 772863 A GB772863 A GB 772863A GB 978375 A GB978375 A GB 978375A
- Authority
- GB
- United Kingdom
- Prior art keywords
- channel
- plug
- fuel elements
- area
- top surface
- 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
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/06—Means for locating or supporting fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- 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
- G21C19/02—Details of handling arrangements
- G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
-
- 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
- G21C19/02—Details of handling arrangements
- G21C19/12—Arrangements for exerting direct hydraulic or pneumatic force on fuel element or on control 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
978,375. Nuclear reactors. EUROPEAN ATOMIC ENERGY COMMUNITY (EURATOM). Feb. 26,1963 [March 1, 1962], No. 7729/63. Heading G6C. Movement of the fuel elements 4 with fluid flow along the vertical coolant channel 1 of a fluid cooled nuclear reactor, which flow is upwards in the direction of the arrows f is prevented by means of a stepped plug 8 sitting in a portion of the channel 1 of enlarged cross-section, the area of the bottom surface of the plug being slightly less than that of the cross-section of the channel 1 while the area of the top surface is greater, a by-pass 10 extending from the bottom of the channel 1 near the cooling fluid entry conduit 2 to the top of the channel 1 above the top surface of the plug 8. The by-pass 10 enables the pressure in the channel 1 below the fuel elements to be exerted on the top surface of the plug 8 and, since the area of this surface is greater than the cross-sectional area of the channel 1, the fuel elements 4 remain in position, a finger 9 at the bottom end of the plug 8 engaging the top fuel element 4. Stop means (not shown) are provided in the channel 1 below the fuel elements 4 to limit their downward movement when they are not supported by the flow of cooling fluid.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR889592A FR1323700A (en) | 1962-03-01 | 1962-03-01 | Device for locking fuel cartridges in a nuclear reactor channel cooled by circulation of pressurized fluid and nuclear reactor provided with this device |
Publications (1)
Publication Number | Publication Date |
---|---|
GB978375A true GB978375A (en) | 1964-12-23 |
Family
ID=8773768
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB7728/63A Expired GB978375A (en) | 1962-03-01 | 1963-02-26 | Improvements in pressure-fluid cooled nuclear reactors |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE628579A (en) |
DE (1) | DE1295714B (en) |
FR (1) | FR1323700A (en) |
GB (1) | GB978375A (en) |
NL (1) | NL289408A (en) |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL102737C (en) * | 1956-08-02 | |||
LU37121A1 (en) * | 1958-05-03 | |||
DE1075231B (en) * | 1959-09-22 | 1960-02-11 | Siemens Schuckertwerke Aktiengesellschaft, Berlin und Erlangen | Heterogeneous nuclear reactor with the moderator room of the reactor rod-like running through guide tubes to accommodate the fissile material elements |
-
0
- NL NL289408D patent/NL289408A/xx unknown
- BE BE628579D patent/BE628579A/xx unknown
-
1962
- 1962-03-01 FR FR889592A patent/FR1323700A/en not_active Expired
-
1963
- 1963-02-19 DE DEE24359A patent/DE1295714B/en active Pending
- 1963-02-26 GB GB7728/63A patent/GB978375A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
BE628579A (en) | |
FR1323700A (en) | 1963-04-12 |
NL289408A (en) | |
DE1295714B (en) | 1969-05-22 |
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