Answers are grounded in this paper and cite their sources.
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.
No takes yet. Share an insight, caveat, or question.
Farkas et al. (2024) studied this question.
Synapse has enriched 10 related papers. Consider them for comparative context: