Numerical study of thermal destruction of nitride fuel rods using the severe accident module of the integral Euclid/V$2$ code

The paper presents approaches that can be used to analyze the behavior of mixed nitride uranium–plutonium fuel rods during emergency situations accompanied by thermal destruction of fuel rods. The validation results based on currently available data are presented. The calculation error was estimated from the validation results. Based on the validated model, the results of a numerical study of the specific features of the breakdown of mixed nitride uranium–plutonium fuel rods are presented for accident conditions typical of reactor plants with sodium and lead coolants.