Research Article

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

Table 9

Selected parameters for comparison in PHS-05 test.

Figure no.LabelDescription

1TE15Heater rod surface temperature at core outlet
2TE63Coolant temperature at core inlet
3TE22Coolant temperature in upper plenum
4TE41Coolant temperature at SG inlet
5TE42Coolant temperature at SG outlet
6PR21Pressure in upper plenum
7PR81Pressure in the SG secondary side
8LE11Coolant collapsed level in the reactor model
9LE71Coolant level in the pressuriser
10LE31Coolant level in the hot leg loop seal, reactor side
11LE45Coolant level in the SG hot collector
12LE46Coolant level in the SG cold collector
13LE52Coolant level in the cold leg loop seal, reactor side
14MA01Integrated mass flow through the break