GB1121979A - An annular fuel element for a nuclear reactor - Google Patents
An annular fuel element for a nuclear reactorInfo
- Publication number
- GB1121979A GB1121979A GB24502/67A GB2450267A GB1121979A GB 1121979 A GB1121979 A GB 1121979A GB 24502/67 A GB24502/67 A GB 24502/67A GB 2450267 A GB2450267 A GB 2450267A GB 1121979 A GB1121979 A GB 1121979A
- Authority
- GB
- United Kingdom
- Prior art keywords
- cladding
- fuel
- plugs
- external
- zircaloy
- 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
- G21C3/10—End closures ; Means for tight mounting therefor
-
- 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
-
- 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
-
- 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)
- Butt Welding And Welding Of Specific Article (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,121,979. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 26 May, 1967 [27 May, 1966], No. 24502/67. Heading G6C. An annular fuel element for a natural uranium reactor cooled by circulation of CO 2 gas in the same direction inside and outside the element comprises a tubular slug of nuclear fuel covered with external and internal cladding, both of which have fins arranged in chevrons and are connected by annular plugs, the external cladding and plugs being made from a Mg-based alloy and the internal cladding from Zr or a Zr-based alloy having a higher hot strength than the Mg alloy. Suitable Zr alloys are Zircaloy ATR (containing, by wt., 0À5% Cu and 0À5% Mo), Zircaloy AJR (containing, by wt., 1% Cu and 1À5% Mo) and Zircaloy-2 (containing, by wt., 1À5% Sn and small additions of Ni, Cr and Fe). The fins on the internal cladding are preferably shallower than those on the external cladding. The external cladding may also have longitudinal partitions for centering the fuel element in a coolant duct. An annular disc of thermally insulating material resistant to creep when hot (e.g. a ceramic) is interposed between each plug and the fuel. The fuel is covered with the cladding members which are then forced against the fuel by any suitable method, e.g. hydraulic cladding after temporary plugging. The permanent plugs are then attached. The cladding members are preferably anchored on circular grooves in the fuel to prevent a ratchet effect during thermal cycling. The plugs are joined to the external cladding by arc-welding in an argon atmosphere or by electron beam welding and to the internal cladding by a process similar to that described in Specification 1,099,025.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR63325A FR1499999A (en) | 1966-05-27 | 1966-05-27 | annular fuel element |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1121979A true GB1121979A (en) | 1968-07-31 |
Family
ID=8609660
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB24502/67A Expired GB1121979A (en) | 1966-05-27 | 1967-05-26 | An annular fuel element for a nuclear reactor |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE698106A (en) |
CH (1) | CH474123A (en) |
ES (1) | ES341051A1 (en) |
FR (1) | FR1499999A (en) |
GB (1) | GB1121979A (en) |
LU (1) | LU53739A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2794744C1 (en) * | 2022-05-04 | 2023-04-24 | Акционерное общество "Электрогорский научно-исследовательский центр по безопасности атомных электростанций" | Method for increating critical heat fluxes in a fuel assembly with tubular fuel rods |
-
1966
- 1966-05-27 FR FR63325A patent/FR1499999A/en not_active Expired
-
1967
- 1967-05-08 BE BE698106D patent/BE698106A/xx unknown
- 1967-05-12 CH CH675067A patent/CH474123A/en not_active IP Right Cessation
- 1967-05-24 LU LU53739D patent/LU53739A1/xx unknown
- 1967-05-26 GB GB24502/67A patent/GB1121979A/en not_active Expired
- 1967-05-27 ES ES341051A patent/ES341051A1/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2794744C1 (en) * | 2022-05-04 | 2023-04-24 | Акционерное общество "Электрогорский научно-исследовательский центр по безопасности атомных электростанций" | Method for increating critical heat fluxes in a fuel assembly with tubular fuel rods |
Also Published As
Publication number | Publication date |
---|---|
CH474123A (en) | 1969-06-15 |
LU53739A1 (en) | 1967-07-24 |
BE698106A (en) | 1967-10-16 |
ES341051A1 (en) | 1968-12-16 |
FR1499999A (en) | 1967-11-03 |
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