GB1048590A - Improvements in or relating to nuclear reactor fuel elements - Google Patents
Improvements in or relating to nuclear reactor fuel elementsInfo
- Publication number
- GB1048590A GB1048590A GB43627/62A GB4362762A GB1048590A GB 1048590 A GB1048590 A GB 1048590A GB 43627/62 A GB43627/62 A GB 43627/62A GB 4362762 A GB4362762 A GB 4362762A GB 1048590 A GB1048590 A GB 1048590A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sheath
- fuel
- graphite
- nuclear reactor
- end caps
- 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 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 5
- 239000000446 fuel Substances 0.000 abstract 5
- 229910002804 graphite Inorganic materials 0.000 abstract 5
- 239000010439 graphite Substances 0.000 abstract 5
- 239000011248 coating agent Substances 0.000 abstract 3
- 238000000576 coating method Methods 0.000 abstract 3
- 239000011229 interlayer Substances 0.000 abstract 3
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 abstract 2
- 229910052778 Plutonium Inorganic materials 0.000 abstract 2
- 229910052770 Uranium Inorganic materials 0.000 abstract 2
- 238000009792 diffusion process Methods 0.000 abstract 2
- 238000007598 dipping method Methods 0.000 abstract 2
- 239000000463 material Substances 0.000 abstract 2
- 238000010422 painting Methods 0.000 abstract 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 abstract 2
- 238000005507 spraying Methods 0.000 abstract 2
- 239000000725 suspension Substances 0.000 abstract 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 2
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 abstract 1
- 239000000956 alloy Substances 0.000 abstract 1
- 229910045601 alloy Inorganic materials 0.000 abstract 1
- 230000004888 barrier function Effects 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 238000010438 heat treatment Methods 0.000 abstract 1
- 229910052749 magnesium Inorganic materials 0.000 abstract 1
- 239000011777 magnesium Substances 0.000 abstract 1
- CRGGPIWCSGOBDN-UHFFFAOYSA-N magnesium;dioxido(dioxo)chromium Chemical group [Mg+2].[O-][Cr]([O-])(=O)=O CRGGPIWCSGOBDN-UHFFFAOYSA-N 0.000 abstract 1
- 238000000034 method Methods 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)
- Carbon And Carbon Compounds (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
1,048,590. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. Oct. 24, 1963 [Nov. 19, 1962], No. 43627/62. Heading G6C. A nuclear reactor fuel element comprising a member of nuclear fuel material enclosed in a sheath of magnesium base alloy which is susceptible to the diffusion therethrough of plutonium resulting from the irradiation of the fuel element in a nuclear reactor has an interlayer disposed between the fuel and the sheath to act as a barrier against diffusion into and through the sheath of plutonium. The interlayer may be a graphite coating on the fuel, or on the inner surface of the sheath and end caps, or both. Where the fuel is a uranium rod, this is cleaned and degreased and then heated in air at 150‹ C. to provide an oxide coating on to which, after cooling, a suspension of graphite in alcohol is applied by spraying, painting or dipping. For coating the sheath and end caps these are cleaned and degreased, dried by heating to 100‹ to 150‹ C., and then have their inner surfaces coated with a suspension of graphite in alcohol by filling and draining (in the case of the sheath) or by spraying, painting or dipping (in the case of the end caps). In an alternative graphiting process for uranium rods, these are grit blasted after which powdered flake graphite is rubbed on to their surfaces. An alternative interlayer material to graphite is magnesium chromate.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB43627/62A GB1048590A (en) | 1962-11-19 | 1962-11-19 | Improvements in or relating to nuclear reactor fuel elements |
| DE19631439819 DE1439819A1 (en) | 1962-11-19 | 1963-11-06 | Nuclear reactor fuel assembly |
| BE640091D BE640091A (en) | 1962-11-19 | 1963-11-18 | |
| FR954153A FR1374857A (en) | 1962-11-19 | 1963-11-18 | Advanced cartridges for nuclear reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB43627/62A GB1048590A (en) | 1962-11-19 | 1962-11-19 | Improvements in or relating to nuclear reactor fuel elements |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1048590A true GB1048590A (en) | 1966-11-16 |
Family
ID=10429618
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB43627/62A Expired GB1048590A (en) | 1962-11-19 | 1962-11-19 | Improvements in or relating to nuclear reactor fuel elements |
Country Status (3)
| Country | Link |
|---|---|
| BE (1) | BE640091A (en) |
| DE (1) | DE1439819A1 (en) |
| GB (1) | GB1048590A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4146431A (en) * | 1974-03-13 | 1979-03-27 | Canadian General Electric Company Limited | Nuclear fuel cladding system |
| US4618406A (en) * | 1978-10-17 | 1986-10-21 | Hitachi, Ltd. | Graphite-coated tube and process for producing the same |
-
1962
- 1962-11-19 GB GB43627/62A patent/GB1048590A/en not_active Expired
-
1963
- 1963-11-06 DE DE19631439819 patent/DE1439819A1/en active Pending
- 1963-11-18 BE BE640091D patent/BE640091A/xx unknown
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4146431A (en) * | 1974-03-13 | 1979-03-27 | Canadian General Electric Company Limited | Nuclear fuel cladding system |
| US4618406A (en) * | 1978-10-17 | 1986-10-21 | Hitachi, Ltd. | Graphite-coated tube and process for producing the same |
Also Published As
| Publication number | Publication date |
|---|---|
| DE1439819A1 (en) | 1969-02-13 |
| BE640091A (en) | 1964-05-19 |
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