GB1330031A - High temperature gas cooled reactor fuel elements - Google Patents
High temperature gas cooled reactor fuel elementsInfo
- Publication number
- GB1330031A GB1330031A GB750771*[A GB1330031DA GB1330031A GB 1330031 A GB1330031 A GB 1330031A GB 1330031D A GB1330031D A GB 1330031DA GB 1330031 A GB1330031 A GB 1330031A
- Authority
- GB
- United Kingdom
- Prior art keywords
- discs
- stack
- coolant
- reactor
- fuel
- 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
- 239000002826 coolant Substances 0.000 abstract 4
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 3
- 239000000446 fuel Substances 0.000 abstract 3
- 229910002804 graphite Inorganic materials 0.000 abstract 3
- 239000010439 graphite Substances 0.000 abstract 3
- 239000000463 material Substances 0.000 abstract 2
- 239000011159 matrix material Substances 0.000 abstract 2
- 239000000919 ceramic Substances 0.000 abstract 1
- 239000002245 particle Substances 0.000 abstract 1
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 abstract 1
- 229910010271 silicon carbide Inorganic materials 0.000 abstract 1
- 125000006850 spacer group Chemical group 0.000 abstract 1
- 230000008646 thermal stress Effects 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
-
- 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)
- Physical Or Chemical Processes And Apparatus (AREA)
- Particle Accelerators (AREA)
Abstract
1330031 Fuel elements UNITED KING- DOM ATOMIC ENERGY AUTHORITY 17 March 1972 [22 March 1971] 7507/71 Heading G6C A nuclear reactor fuel element, particularly for a high temperature gas-cooled reactor, comprises a tubular member composed of a stack of nuclear fuel-containing annular discs 2 with provision for coolant to flow between adjacent discs. The discs 2 each have a central hole of uniform bore while their outer diameters gradually increase from the lower end to the upper end of the stack. The discs 2 are centred on a porous ceramic or wire mesh sleeve 3, and the resultant stack is enclosed peripherally by a similar but gradually tapered outer sleeve 4. Each disc 2 is composed of a double layer of coated fissile fuel particles 2a embedded in a graphite matrix, and moulded in graphite on the underside of each disc are three radial ribs 5 which act as spacers. These ribs 5 coincide with three unfuelled radial zones in the adjacent discs 2 of the stack. Coolant gas flows from a pressure gas supply plenum 7 to an outlet plenum 8, passing in turn through the outer sleeve 4, the coolant spaces between adjacent discs 2, the inner sleeve 3, and the centre bore of the stack. The upper and lower regions A and B are occupied by unfuelled graphite to act as a reflector for operation in a thermal reactor, or by fertile material for operation in a fast reactor. In either use, the material in these regions may be formed as ribbed discs so as to be cooled in a similar manner to the fissile fuel. Alternative matrix materials are silicon carbide and pyrocarbon. Where the discs may be subjected to such thermal gradients as will set up unaccept- ably high thermal stresses, radial gaps are formed in the discs to prevent their fracture. In a modified form, part conical annular discs are employed instead of flat annular discs. In either case, the coolant flow direction may be the reverse of that described above.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB750771 | 1971-03-22 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1330031A true GB1330031A (en) | 1973-09-12 |
Family
ID=9834449
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB750771*[A Expired GB1330031A (en) | 1971-03-22 | 1971-03-22 | High temperature gas cooled reactor fuel elements |
Country Status (7)
Country | Link |
---|---|
BE (1) | BE780633A (en) |
DE (1) | DE2213026A1 (en) |
FR (1) | FR2130516B1 (en) |
GB (1) | GB1330031A (en) |
IT (1) | IT952168B (en) |
LU (1) | LU64994A1 (en) |
NL (1) | NL7203223A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20190108920A1 (en) * | 2017-10-10 | 2019-04-11 | Howe Industries, Llc | Customizable thin plate fuel form and reactor core therefor |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5089219A (en) * | 1991-01-22 | 1992-02-18 | The Babcock & Wilcox Company | Gas cooled nuclear fuel element |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE562087A (en) * | 1956-11-01 |
-
1971
- 1971-03-22 GB GB750771*[A patent/GB1330031A/en not_active Expired
-
1972
- 1972-03-08 IT IT48853/72A patent/IT952168B/en active
- 1972-03-10 NL NL7203223A patent/NL7203223A/xx unknown
- 1972-03-14 BE BE780633A patent/BE780633A/en unknown
- 1972-03-14 DE DE19722213026 patent/DE2213026A1/en active Pending
- 1972-03-20 LU LU64994D patent/LU64994A1/xx unknown
- 1972-03-21 FR FR7209903A patent/FR2130516B1/fr not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20190108920A1 (en) * | 2017-10-10 | 2019-04-11 | Howe Industries, Llc | Customizable thin plate fuel form and reactor core therefor |
US11139086B2 (en) * | 2017-10-10 | 2021-10-05 | Howe Industries, Llc | Customizable thin plate fuel form and reactor core therefor |
US11923098B2 (en) | 2017-10-10 | 2024-03-05 | Howe Industries, Llc | Customizable thin plate fuel form and reactor core therefor |
Also Published As
Publication number | Publication date |
---|---|
FR2130516A1 (en) | 1972-11-03 |
IT952168B (en) | 1973-07-20 |
NL7203223A (en) | 1972-09-26 |
FR2130516B1 (en) | 1974-12-13 |
LU64994A1 (en) | 1972-07-10 |
BE780633A (en) | 1972-07-03 |
DE2213026A1 (en) | 1972-10-05 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |