Thermionic Fuel Element with Cermet Fuel

A method of calculating and the computational results obtained for the time variation of the radial deformation of the fuel-element cladding of a single-element EGC based on cermet with a polycrystalline molybdenum matrix in which uranium dioxide particles are distributed are presented. It is shown...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2018-10, Vol.124 (6), p.392-397
Main Authors: Gontar’, A. S., Nelidov, M. V., Sotnikov, V. N.
Format: Article
Language:English
Subjects:
CERMETS
CLADDING
Computer applications
Deformation
Energy industry
FUEL ELEMENTS
FUELS
GENERAL STUDIES OF NUCLEAR REACTORS
Hadrons
Heavy Ions
MOLYBDENUM
Nuclear Chemistry
Nuclear Energy
Nuclear fuels
Nuclear Physics
Nuclear power plants
Physics
Physics and Astronomy
Polycrystals
Single crystals
SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Tantalum
TANTALUM ALLOYS
Tantalum base alloys
TUNGSTEN
Tungsten base alloys
Uranium
URANIUM DIOXIDE
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Summary:A method of calculating and the computational results obtained for the time variation of the radial deformation of the fuel-element cladding of a single-element EGC based on cermet with a polycrystalline molybdenum matrix in which uranium dioxide particles are distributed are presented. It is shown that the maximum admissible deformation of cladding comprised of 1-mm thick, hardened, single-crystalline, tungsten-tantalum alloy with a 10 mm in diameter central channel in the kernel is reached in 10 years.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-018-0428-z