GB859940A - Improvements in or relating to nuclear fuel elements - Google Patents
Improvements in or relating to nuclear fuel elementsInfo
- Publication number
- GB859940A GB859940A GB4870/49A GB487049A GB859940A GB 859940 A GB859940 A GB 859940A GB 4870/49 A GB4870/49 A GB 4870/49A GB 487049 A GB487049 A GB 487049A GB 859940 A GB859940 A GB 859940A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- graphite
- nuclear fuel
- fuel elements
- feb
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 229910052770 Uranium Inorganic materials 0.000 abstract 4
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 3
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 abstract 3
- KRKNYBCHXYNGOX-UHFFFAOYSA-N citric acid Chemical compound OC(=O)CC(O)(C(O)=O)CC(O)=O KRKNYBCHXYNGOX-UHFFFAOYSA-N 0.000 abstract 3
- 229910002804 graphite Inorganic materials 0.000 abstract 3
- 239000010439 graphite Substances 0.000 abstract 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 3
- CSCPPACGZOOCGX-UHFFFAOYSA-N Acetone Chemical compound CC(C)=O CSCPPACGZOOCGX-UHFFFAOYSA-N 0.000 abstract 2
- 239000000126 substance Substances 0.000 abstract 2
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 abstract 1
- XSTXAVWGXDQKEL-UHFFFAOYSA-N Trichloroethylene Chemical group ClC=C(Cl)Cl XSTXAVWGXDQKEL-UHFFFAOYSA-N 0.000 abstract 1
- 239000011248 coating agent Substances 0.000 abstract 1
- 238000000576 coating method Methods 0.000 abstract 1
- 229910052802 copper Inorganic materials 0.000 abstract 1
- 238000005238 degreasing Methods 0.000 abstract 1
- 238000009792 diffusion process Methods 0.000 abstract 1
- 238000001704 evaporation Methods 0.000 abstract 1
- 238000010438 heat treatment Methods 0.000 abstract 1
- 229910052751 metal Inorganic materials 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 238000007747 plating Methods 0.000 abstract 1
- 229910052709 silver Inorganic materials 0.000 abstract 1
- 239000002904 solvent Substances 0.000 abstract 1
- 239000000725 suspension Substances 0.000 abstract 1
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
- G21C3/16—Details of the construction within the casing
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
-
- 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)
- Chemically Coating (AREA)
Abstract
859,940. Nuclear fuel elements. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 17, 1950 [Feb. 22, 1949], No. 4870/49. Class 39(4). A mass of uranium enclosed in an Al can is separated from the can by a layer of a substance which prevents contact or diffusion of the U and Al. The substance may be graphite, Cu, Ag, and may be applied to the uranium, the can or both ; where graphite is used the uranium may first be oxidised at its surface by heating in air after degreasing in acetone and anodic treatment in aqueous citric acid solution. The cans are cleaned by treatment with trichlorethylene, with warm dilute NaOH solution and with dilute HNO 3 . Graphite is applied as a suspension in a volatile solvent, preferably alcohol. A metal coating may be applied by standard plating or evaporation methods. Specification 811,432 is referred to.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB4870/49A GB859940A (en) | 1949-02-22 | 1949-02-22 | Improvements in or relating to nuclear fuel elements |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB4870/49A GB859940A (en) | 1949-02-22 | 1949-02-22 | Improvements in or relating to nuclear fuel elements |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB859940A true GB859940A (en) | 1961-01-25 |
Family
ID=9785366
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4870/49A Expired GB859940A (en) | 1949-02-22 | 1949-02-22 | Improvements in or relating to nuclear fuel elements |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB859940A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3212988A (en) * | 1961-07-18 | 1965-10-19 | Ringot Claude | Fuel element for nuclear reactors |
| DE1286228B (en) * | 1964-08-07 | 1969-01-02 | Union Carbide Corp | Method of manufacturing a nuclear fuel element |
-
1949
- 1949-02-22 GB GB4870/49A patent/GB859940A/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3212988A (en) * | 1961-07-18 | 1965-10-19 | Ringot Claude | Fuel element for nuclear reactors |
| DE1286228B (en) * | 1964-08-07 | 1969-01-02 | Union Carbide Corp | Method of manufacturing a nuclear fuel element |
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