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

The possibility of using UO{sub 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{sub 2}-BeO fuel pellets are estimated.
Authors:
; ;  [1] ;  [2]
  1. National Research Center Kurchatov Institute (Russian Federation)
  2. National Research Nuclear University MEPhI (Russian Federation)
Publication Date:
OSTI Identifier:
22314713
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 77; Journal Issue: 14; Other Information: Copyright (c) 2014 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BERYLLIUM OXIDES; FUEL ASSEMBLIES; FUEL PELLETS; NEUTRONS; NUCLEAR FUELS; URANIUM DIOXIDE; WWER TYPE REACTORS