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

<table>Cladding temperatures TE15, TE16, TE17, saturation temperature (TS01) and coolant collapsed level in the core model (LE11), in PH4-SLB, 32% break in the surge line at the hot leg connection. </table>

Science and Technology of Nuclear Installations

fig17

Figure 17

Figure 17: PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants 