GB1071411A - Improvements in or relating to fuel elements for nuclear reactors - Google Patents
Improvements in or relating to fuel elements for nuclear reactorsInfo
- Publication number
- GB1071411A GB1071411A GB3694/63A GB369463A GB1071411A GB 1071411 A GB1071411 A GB 1071411A GB 3694/63 A GB3694/63 A GB 3694/63A GB 369463 A GB369463 A GB 369463A GB 1071411 A GB1071411 A GB 1071411A
- Authority
- GB
- United Kingdom
- Prior art keywords
- canning
- die
- billet
- rod
- enclosing
- 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
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
- G21C21/12—Manufacture of fuel elements or breeder elements contained in non-active casings by hydrostatic or thermo-pneumatic canning in general by pressing without lengthening, e.g. explosive coating
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,071,411. Forging. CENTRAL ELECTRICITY GENERATING BOARD. Jan. 29, 1964 [Jan. 29, 1963], No. 3694/63. Heading B3H. [Also in Division G6] A nuclear reactor fuel element is formed by completely enclosing a rigid rod of fissile material in an integral can. The enclosing is carried out in a die by means of a high-speed, highenergy process, utilizing for example high or low explosives, electro-hydraulic or electromagnetic discharge, or a stored energy pneumatic process. The fuel rod may be solid, e.g. uranium, or composted powder. The canning is preferably a magnesium alloy, but a composite canning billet may be employed to give different properties along the can; the wall thickness may also be varied. The can may also be powdered metal, composted either before or during the coming process. The canning material may be preheated, before or after being placed in the die. Referring to Fig. 1, the billet 12 is placed in the die 10 and the fuel rod 11 and former 14 forced into the billet and die respectively, thus totally enclosing the rod as seen in Fig. 2. The grooves 17 are to prevent ratchetting; the combination of the forming pressure and temperature difference (hot canning billet) results in excellent heat transfer across the interface. Canning may be carried out in a vacuum, or non-oxidizing atmosphere. The die may include longitudinal recesses for forming baffles and splitters (e.g. 26 in Fig. 8, not shown). Fig. 7 shows a fuel element machined from Fig. 2 and including a stabilizing spider 23, the fins may alternatively be of herring-bone pattern. In an alternative method of canning (Fig. 3, not shown), a tubular billet of canning metal is placed in a die having both ends open, and a clearance fit fuel rod placed in it; formers are forced into both ends of the die simultaneously. Helium gas, or a radioactive clathrate compound can be included in the can for leak detection purposes.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3694/63A GB1071411A (en) | 1963-01-29 | 1963-01-29 | Improvements in or relating to fuel elements for nuclear reactors |
FR961974A FR1381765A (en) | 1963-01-29 | 1964-01-29 | Improvements to fuel cartridges for nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3694/63A GB1071411A (en) | 1963-01-29 | 1963-01-29 | Improvements in or relating to fuel elements for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1071411A true GB1071411A (en) | 1967-06-07 |
Family
ID=9763191
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3694/63A Expired GB1071411A (en) | 1963-01-29 | 1963-01-29 | Improvements in or relating to fuel elements for nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1071411A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2168192A (en) * | 1984-12-07 | 1986-06-11 | Atomic Energy Authority Uk | Gas cooled nuclear reactors |
-
1963
- 1963-01-29 GB GB3694/63A patent/GB1071411A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2168192A (en) * | 1984-12-07 | 1986-06-11 | Atomic Energy Authority Uk | Gas cooled nuclear reactors |
GB2168192B (en) * | 1984-12-07 | 1989-08-31 | Atomic Energy Authority Uk | Gas cooled nuclear reactors |
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