On the possibility of using uranium-beryllium oxide fuel in a VVER reactor

The possibility of using UO 2 -BeO fuel in a VVER reactor is considered with allowance for the thermophysical properties of this fuel. Neutron characteristics of VVER fuel assemblies with UO 2 -BeO fuel pellets are estimated.

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Bibliographic Details
Published in:Physics of atomic nuclei 2014-12, Vol.77 (14), p.1661-1663
Main Authors: Kovalishin, A. A., Prosyolkov, V. N., Sidorenko, V. D., Stogov, Yu. V.
Format: Article
Language:English
Subjects:
Beryllium
BERYLLIUM OXIDES
Electric properties
FUEL ASSEMBLIES
FUEL PELLETS
NEUTRONS
NUCLEAR FUELS
Particle and Nuclear Physics
Physics
Physics and Astronomy
SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Uranium
URANIUM DIOXIDE
WWER TYPE REACTORS
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Description
Summary:The possibility of using UO 2 -BeO fuel in a VVER reactor is considered with allowance for the thermophysical properties of this fuel. Neutron characteristics of VVER fuel assemblies with UO 2 -BeO fuel pellets are estimated.
ISSN:1063-7788
1562-692X
DOI:10.1134/S1063778814140063