GB1268186A - Improvements in or relating to nuclear reactor fuel elements - Google Patents
Improvements in or relating to nuclear reactor fuel elementsInfo
- Publication number
- GB1268186A GB1268186A GB33902/68A GB3390268A GB1268186A GB 1268186 A GB1268186 A GB 1268186A GB 33902/68 A GB33902/68 A GB 33902/68A GB 3390268 A GB3390268 A GB 3390268A GB 1268186 A GB1268186 A GB 1268186A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- interlayers
- fissile
- sheathing
- interlayer
- 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 1
- 239000000446 fuel Substances 0.000 abstract 19
- 239000011229 interlayer Substances 0.000 abstract 9
- 239000000919 ceramic Substances 0.000 abstract 6
- 150000001875 compounds Chemical class 0.000 abstract 5
- 239000010410 layer Substances 0.000 abstract 5
- 239000008188 pellet Substances 0.000 abstract 5
- 230000004992 fission Effects 0.000 abstract 4
- 230000000155 isotopic effect Effects 0.000 abstract 2
- 239000000463 material Substances 0.000 abstract 2
- 239000002245 particle Substances 0.000 abstract 2
- 229910010413 TiO 2 Inorganic materials 0.000 abstract 1
- 230000004308 accommodation Effects 0.000 abstract 1
- 238000007598 dipping method Methods 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 238000005507 spraying Methods 0.000 abstract 1
- 230000008961 swelling Effects 0.000 abstract 1
- 238000013022 venting Methods 0.000 abstract 1
Classifications
-
- H—ELECTRICITY
- H01—ELECTRIC ELEMENTS
- H01B—CABLES; CONDUCTORS; INSULATORS; SELECTION OF MATERIALS FOR THEIR CONDUCTIVE, INSULATING OR DIELECTRIC PROPERTIES
- H01B1/00—Conductors or conductive bodies characterised by the conductive materials; Selection of materials as conductors
- H01B1/20—Conductive material dispersed in non-conductive organic material
- H01B1/24—Conductive material dispersed in non-conductive organic material the conductive material comprising carbon-silicon compounds, carbon or silicon
-
- 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
-
- 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
-
- 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
-
- 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
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
-
- 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)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,268,186. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 21 April, 1969 [26 April, 1968; 16 July, 1968], Nos. 20041/68 and 33902/68. Addition to 1,174,575. Heading G6C. A fuel element of the type specified in the main parent Specification is, in one feature of the invention, in the form of an elongate fuel member and its metallic sheathing includes both internal and external sheathing between which the fuel is disposed, the fuel member thus being of the tubular type and there being an interlayer disposed between and directly contacting the fuel and each of the internal and external sheathing. The interlayers are preferably of a ceramic compound of U of either natural or depleted fissile isotopic abundance, and the fuel is a ceramic compound of Pu, a mixture of ceramic compounds of U and Pu, or a fissile-enriched ceramic compound of U. The interlayers may be in pellet form with the fuel in the form of vibro-compacted ceramic particles, or the interlayers may be of vibrocompacted ceramic particles and the fuel in pellet form, or the interlayers and the fuel may all be in pellet form. Where the fuel is of pellet form, it may be in two annular portions with an annular gap therebetween to provide a fission product reservoir and enable gaseous fission products the better to pass to a gaseous fission product plenum at one end of the fuel element or to gaseous fission product venting means, and also to assist in providing voidage for the accommodation of irradiation-induced swelling. The fuel density is preferably less than 85% of maximum theoretical density. In one embodiment, each fuel pellet has at least three radial ribs extending from its inner and outer surfaces to contact the sheaths, the part-annular spaces between the ribs being occupied by vibrocompacted UO 2 to form the interlayers. Where the fuel is of carbide compounds, a thin, non- fissile, non-fertile compatibility layer is provided between each interlayer and the respective sheathing over at least that axial region of the fuel zone of the fuel member which is subjected to maximum burn-up in operation. Suitable materials for the compatibility layer include MgO, TiO 2 and ZrO 2 . This layer may be applied by spraying or dipping, those parts outside the axial region of maximum burn-up not requiring the layer being masked. Where the fuel member is not of the tubular type, as according to another feature of the invention, it has its interlayer of UC of natural or depleted fissile isotopic abundance, its fuel of PuC, mixed PuC and UC, or enriched UC, and there is additionally provided between the interlayer and the sheathing, a thin compatibility layer of non-fissile, non-fertile material, such as is described with reference to the firstmentioned feature.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6931964A JPS5322239B1 (en) | 1968-04-26 | 1969-04-24 | |
DE1921203A DE1921203C3 (en) | 1965-12-23 | 1969-04-25 | Fuel assembly for a nuclear reactor |
FR6913342A FR2009838A2 (en) | 1968-04-26 | 1969-04-25 | Fuel cartridges for nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2004168 | 1968-04-26 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1268186A true GB1268186A (en) | 1972-03-22 |
Family
ID=10139371
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB33902/68A Expired GB1268186A (en) | 1965-12-23 | 1968-04-26 | Improvements in or relating to nuclear reactor fuel elements |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1268186A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102640230A (en) * | 2009-10-08 | 2012-08-15 | 法国原子能及替代能源委员会 | Body for a nuclear fuel assembly, and nuclear fuel assembly comprising such a body |
-
1968
- 1968-04-26 GB GB33902/68A patent/GB1268186A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102640230A (en) * | 2009-10-08 | 2012-08-15 | 法国原子能及替代能源委员会 | Body for a nuclear fuel assembly, and nuclear fuel assembly comprising such a body |
US9589681B2 (en) | 2009-10-08 | 2017-03-07 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Nuclear fuel assembly body and a nuclear fuel assembly with such a body |
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