GB1048590A - Improvements in or relating to nuclear reactor fuel elements - Google Patents

Improvements in or relating to nuclear reactor fuel elements

Info

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
Application number
GB43627/62A
Inventor
Richard Arthur Shaw
Gilbert Northcott Walton
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
Priority to GB43627/62A priority Critical patent/GB1048590A/en
Priority to DE19631439819 priority patent/DE1439819A1/en
Priority to FR954153A priority patent/FR1374857A/en
Priority to BE640091D priority patent/BE640091A/xx
Publication of GB1048590A publication Critical patent/GB1048590A/en
Expired legal-status Critical Current

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)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Carbon And Carbon Compounds (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.
GB43627/62A 1962-11-19 1962-11-19 Improvements in or relating to nuclear reactor fuel elements Expired GB1048590A (en)

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
FR954153A FR1374857A (en) 1962-11-19 1963-11-18 Advanced cartridges for nuclear reactors
BE640091D BE640091A (en) 1962-11-19 1963-11-18

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)

* Cited by examiner, † Cited by third party
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

Cited By (2)

* Cited by examiner, † Cited by third party
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
BE640091A (en) 1964-05-19
DE1439819A1 (en) 1969-02-13

Similar Documents

Publication Publication Date Title
GB754183A (en) Improvements in nuclear-chain reactors
ES442000A1 (en) Nuclear fuel element
GB648293A (en) Methods of and apparatus for utilization of the thermal energy released in the course of atomic decompositions
GB1048590A (en) Improvements in or relating to nuclear reactor fuel elements
GB911593A (en) Nuclear fuel element construction
US3409504A (en) Nuclear fuel element
GB1084750A (en) Improvements in nuclear fuel elements
DE1964985A1 (en) Zirconium-coated uranium carbide pellets as
US2924877A (en) Method of jacketing a fissionable body
GB980727A (en) Method of applying metallic coatings
GB903260A (en) Improvements in or relating to a graphite or carbon article
WO1995008827A1 (en) Nuclear fuel sintered body and process for producing it
GB917015A (en) Neutron-absorbing construction-parts for nuclear reactors and procedure for the manufacture
GB966144A (en) Shielding arrangement for nuclear reactors
GB875832A (en) Improvements in or relating to nuclear reactor fuel elements
GB989393A (en) Improvements in or relating to nuclear reactor fuel elements
GB920795A (en) Improvements in or relating to nuclear reactors and fuel alloys therefor
GB829436A (en) Improvements in or relating to nuclear reactors
GB1157226A (en) Method of Internally Carburizing Tantalum Tubes
GB1069187A (en) Coating process
GB1052166A (en) Coating process for uranium rods
GB1249336A (en) A method of producing coated particles
GB794671A (en) Improvements in or relating to the bonding of zirconium to other metals
GB859206A (en) Improvements relating to the canning of fuel elements for use in nuclear reactors
GB835132A (en) Improvements in or relating to fuel elements for nuclear reactors