Physics of Atomic Nuclei · 2014 · 10 citations · 7 references
EngineeringNuclear EngineeringPhysicsNuclear MaterialsNuclear PhysicsReactor PhysicsNuclear FissionNuclear Fuel MaterialsReactor Core DesignReactor DesignReactor Lattice PhysicsThermal Reactor PhysicsBeryllium-based MaterialsThermophysical PropertiesThermophysical Property MeasurementThorium Oxide FuelUranium DioxideUranium Dioxide Fuel PelletsUranium Dioxide FuelsUranium Oxide Fuel
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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Thermophysical properties of uranium dioxide
J.K. Fink · Journal of Nuclear Materials · 2000 · 724 citations
Thermal Conductivity of UO<sub>2</sub>-BeO Pellet
Shinji Ishimoto, Mutsumi Hirai, Kenichi Ito et al. · Journal of Nuclear Science and Technology · 1996 · 75 citations · Full text
Thermal Conductivity of UO2-BeO Pellet.
Shinji Ishimoto, Mutsumi Hirai, Kenichi Ito et al. · Journal of Nuclear Science and Technology · 1996 · 54 citations