Incidental and accidental conditions
Thermomecanics of fuel for pressurized water reactors

Most of the accident studies presented in the nuclear reactor safety report include an analysis of the consequences of these accidents on the performance of the fuel assembly and, more specifically, the fuel rod.

In incidental conditions (transients involving an emergency shutdown triggered by the core protection system), in addition to checking that the limiting stress criterion leading to cladding cracking as a result of pellet-cladding interaction is met (see paragraph 1.5