PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

<table>Cladding temperature TE15, TE16, TE17, saturation temperature (TS01) and coolant collapsed level in the core model (LE11), in OAH-C1, 2% cold leg break without HPIS, with secondary bleed.</table>

Science and Technology of Nuclear Installations

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Figure 9

Figure 9: PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants 