GB1162578A - Improvements in and relating to a Nuclear Reactor Fuel Element Assembly - Google Patents
Improvements in and relating to a Nuclear Reactor Fuel Element AssemblyInfo
- Publication number
- GB1162578A GB1162578A GB31641/67A GB3164167A GB1162578A GB 1162578 A GB1162578 A GB 1162578A GB 31641/67 A GB31641/67 A GB 31641/67A GB 3164167 A GB3164167 A GB 3164167A GB 1162578 A GB1162578 A GB 1162578A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- sleeve
- pencils
- tie
- rods
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/3213—Means for the storage or removal of fission gases
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,162,578. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 10 July, 1967 [12 Aug., 1966]. No. 31641/67. Heading G6C. A transverse support grid for a cluster-type fuel element assembly is formed of spigot rings 5 which fit over and are secured to the upper ends of the fuel pencils 1 and coupling members 11 which connect each ring 5 to at least one adjacent ring and have internal ducts 12 for providing communication between spaces 4 between the cans 2 and the fuel 3 at the upper ends of the fuel pencils 1. A number of solid discs 13 are disposed around the periphery of the support grid and engage in recesses 15 in tie-rods 14. The tie-rods 14 are coupled to each other by means of a metallic sleeve 16 welded to the tie-rods at 17 and surrounded by an outer metallic sleeve 18. The two sleeves 16, 18 are coupled together at one end by means of a circular collar 19 and at the other end by means of a circular collar 46. At this latter end, the sleeve 18 terminates short of the sleeve 16. The ends of each tie-rod 14 are so shaped (Fig. 3, not shown) as to provide a male portion and a female portion, with the result that the tierods of two fuel element assemblies which are superposed in a nuclear reactor fuel channel can be interengaged and the fuel pencils of each cluster axially positioned in the line of extension of each other. The spigot rings 5 are closed at the top by caps 8. The ducts 12 of the coupling members 11 and a number of peripheral fuel pencils 1 are connected to funnel-type components 24 in each of which is formed an axial bore 25 closed at the top by a cap 26. Each component 24 has an arm 27 engaging in a recess 28 of the circular collar 19 and provided with an internal duct 29 through which fission product gases released from the fuel pencils 1 are conveyed to an expansion chamber 30 located between the two sleeves 16, 18. The chamber 30 is delimited by a casing 31 applied against the outer sleeve 18 and a casing 32 separated from the inner sleeve 16 by a layer 34 of heat-insulating material. The two casings 31, 32 are sufficiently thin to deform under the effect of variations of pressure. In the position shown in Fig. 2, the volume of chamber 30 is a maximum as during normal operation. In the event of a shut-down, the two casings 31, 32 can contract and thereby reduce the volume of chamber 30. The fuel cluster is completed at the lower end of the fuel pencils by a member which permits of free expansion of the pencils. The cans 2 are sealed at their lower end by end caps 35 in each of which is formed a blind-end bore 36 in which is mounted a ball 37 and a stud 38. After insertion through seals 39, the studs are secured to a simple grid 40, the ends 41 of which are fitted in a channel 42 formed at the base of the tie-rods 14. Each fuel pencil 1 is divided at the centre by a plug provided with radial fins for the purpose of bracing the fuel cluster. The collar 46 formed either of graphite or silica is radially proud of the sleeve 18 and is applied against the wall of the fuel channel to prevent any coolant flowing between the channel wall and the sleeve 18. The cans 2 may be formed of Zr alloy, Be, Si, graphite or SiC whilst the tie-rods 14 may be formed of impregnated graphite, Si or SiC and the support grids and sleeves 16, 18 of Nb, Zr alloy or steel.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR73050 | 1966-08-12 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1162578A true GB1162578A (en) | 1969-08-27 |
Family
ID=8615385
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB31641/67A Expired GB1162578A (en) | 1966-08-12 | 1967-07-10 | Improvements in and relating to a Nuclear Reactor Fuel Element Assembly |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE700223A (en) |
ES (1) | ES344070A1 (en) |
FR (1) | FR1604122A (en) |
GB (1) | GB1162578A (en) |
LU (1) | LU54284A1 (en) |
NL (1) | NL6710982A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2163888A (en) * | 1984-08-30 | 1986-03-05 | Atomic Energy Authority Uk | Fission gas plenum chamber for nuclear fuel element sub-assembly |
GB2163889A (en) * | 1984-08-30 | 1986-03-05 | Atomic Energy Authority Uk | Fuel assembly |
-
1966
- 1966-08-12 FR FR1604122D patent/FR1604122A/en not_active Expired
-
1967
- 1967-06-20 BE BE700223D patent/BE700223A/xx unknown
- 1967-07-10 GB GB31641/67A patent/GB1162578A/en not_active Expired
- 1967-08-09 NL NL6710982A patent/NL6710982A/xx unknown
- 1967-08-09 LU LU54284D patent/LU54284A1/xx unknown
- 1967-08-12 ES ES344070A patent/ES344070A1/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2163888A (en) * | 1984-08-30 | 1986-03-05 | Atomic Energy Authority Uk | Fission gas plenum chamber for nuclear fuel element sub-assembly |
GB2163889A (en) * | 1984-08-30 | 1986-03-05 | Atomic Energy Authority Uk | Fuel assembly |
Also Published As
Publication number | Publication date |
---|---|
NL6710982A (en) | 1968-02-13 |
FR1604122A (en) | 1971-07-12 |
LU54284A1 (en) | 1967-10-09 |
BE700223A (en) | 1967-12-01 |
ES344070A1 (en) | 1968-12-16 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |