Abstract
The results of experiments performed in the research reactors HBWR (Norway) and MIR (Dimitrovgrad, Russia) with different variants of pelleted uranium dioxide fuel used in VVER and manufactured by Elektrostal MSZ and PWR using a standard method are analyzed. The analysis of the experiments made possible to study the effect of microstructural parameters on the thermomechanical behavior of the experimental fuel elements with this type of fuel. The experimental data on the temperature, length of a fuel kernel, and gas pressure beneath the fuel-element cladding can be used to verify models and thermomechanical codes describing the behavior of VVER fuel elements.
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