Abstract
The analysis of postulated accidents in nuclear power plants is carried out by computer codes that must be validated by experimental results. Experiments were performed on the PMK-NVH facility, a scaled-down model of the primary circuit of the Paks nuclear power plant equipped with WWER-440 reactors. This work presents the results of three experiments with a cold-leg break modeling a 7.4% break in the plant starting from nominal operating conditions with different emergency core cooling systems in action. As examples, some results of code validation are presented. The adequacy of the emergency core cooling systems is evaluated.
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