A loss-of-coolant accident in a nuclear power plant was simulated in the CODEX-SLIM experiment. The electrically heated fuel rod bundle contained cladding material used at a VVER-440 power plant. The maximum temperature reached 900 °C and the experiment was terminated by water quenching. The condition of the bundle was investigated using non-destructive and destructive techniques. According to the experimental data, the fuel rods would maintain their integrity during a design basis loss-of-coolant accident.
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