ES309064A1 - Improvements in or relating to nuclear reactor fuel elements - Google Patents
Improvements in or relating to nuclear reactor fuel elementsInfo
- Publication number
- ES309064A1 ES309064A1 ES0309064A ES309064A ES309064A1 ES 309064 A1 ES309064 A1 ES 309064A1 ES 0309064 A ES0309064 A ES 0309064A ES 309064 A ES309064 A ES 309064A ES 309064 A1 ES309064 A1 ES 309064A1
- Authority
- ES
- Spain
- Prior art keywords
- sheath
- substance
- aluminium
- fuel
- plutonium
- 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
- 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)
- Solid-Phase Diffusion Into Metallic Material Surfaces (AREA)
Abstract
A fuel element, comprising a uranium or uranium base alloy in a sheath of a magnesium base alloy also containing zirconium, has a substance diffused through at least part of the sheath wall thickness which prevents diffusion of plutonium through the sheath by forming an intermetallic compound with the plutonium. The substance is preferably aluminium, although it may alternatively be aluminium-silicon, copper, nickel, or copper and nickel based alloys. The substance is preferably applied initially to the fuel body in the form of a wrapping of foil, although it can be applied to the sheath interior, and may in both cases be applied alternatively by vacuum deposition, electro deposition, spraying or dipping. The fuel and sheath are assembled with a layer of the substance between them, and heat and pressure applied. In the case of aluminium, it forms an intermetallic compound with the sheath zirconium, and consequently sufficient aluminium must be used to ensure that an uncompounded layer has diffused into the can which will combine with the plutonium as it is formed during fission of the fuel element. The diffusion is not necessarily completed during manufacture it may continue to take place from the remaining layer between the fuel and sheath during use in the reactor.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5172/64A GB1063631A (en) | 1964-02-06 | 1964-02-06 | Improvements in or relating to nuclear reactor fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
ES309064A1 true ES309064A1 (en) | 1966-03-16 |
Family
ID=9791054
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES0309064A Expired ES309064A1 (en) | 1964-02-06 | 1965-02-06 | Improvements in or relating to nuclear reactor fuel elements |
Country Status (3)
Country | Link |
---|---|
ES (1) | ES309064A1 (en) |
FR (1) | FR1424095A (en) |
GB (1) | GB1063631A (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4045288A (en) * | 1974-11-11 | 1977-08-30 | General Electric Company | Nuclear fuel element |
ES440476A1 (en) * | 1974-11-11 | 1977-09-01 | Gen Electric | Nuclear fuel elements |
US4029545A (en) * | 1974-11-11 | 1977-06-14 | General Electric Company | Nuclear fuel elements having a composite cladding |
US4316771A (en) * | 1978-01-17 | 1982-02-23 | Canadian General Electric Company Limited | Nuclear fuel stress corrosion prevention |
EA033850B8 (en) * | 2018-10-31 | 2020-01-22 | Федеральное государственное унитарное предприятие "Научно-исследовательский институт Научно-производственное объединение "ЛУЧ" (ФГУП "НИИ НПО "ЛУЧ") | Method for producing dispersion-type fuel element and fuel pellets based thereon |
-
1964
- 1964-02-06 GB GB5172/64A patent/GB1063631A/en not_active Expired
-
1965
- 1965-02-02 FR FR4147A patent/FR1424095A/en not_active Expired
- 1965-02-06 ES ES0309064A patent/ES309064A1/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
FR1424095A (en) | 1966-01-07 |
GB1063631A (en) | 1967-03-30 |
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