ES309064A1 - Improvements in or relating to nuclear reactor fuel elements - Google Patents

Improvements in or relating to nuclear reactor fuel elements

Info

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
Application number
ES0309064A
Other languages
Spanish (es)
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of ES309064A1 publication Critical patent/ES309064A1/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/20Details 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
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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.
ES0309064A 1964-02-06 1965-02-06 Improvements in or relating to nuclear reactor fuel elements Expired ES309064A1 (en)

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)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
FR1424095A (en) 1966-01-07
GB1063631A (en) 1967-03-30

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