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

Figure 7

Cladding temperatures TE10, TE11, TE12, saturation temperature (TS01) and coolant collapsed level in the core model (LE11), in OAH-C1, 2% cold leg break without HPIS, with secondary bleed.