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Storage of Thermal REactor Safety Analysis data

The activities covered the following three areas:

  • Thermal hydraulic calculations described the cooling conditions possibly established during the incident.
  • Simulation of fuel behaviour described the oxidation and degradation mechanisms of fuel assemblies.
  • The release of fission products from the failed fuel rods was estimated and compared to available measured data.

The produced numerical results improved the understanding of the causes and mechanisms of fuel failures during the Paks-2 incident and provided new information on the behaviour of nuclear fuel under accident conditions.

Type of Facility
Thermal Hydraulics
Experiments available