Simulation of tube rupture in steam generator and transient analysis of VVER-1200 using PCTRAN

The objective of this paper is to present and analyze the results of simulated steam generator tube rupture (SGTR) accident in VVER-1200 Nuclear Reactor in PCTRAN. In simulating the accident, 100% of one full tube rupture has been considered. The simulation result shows that pressure and temperature changes slightly but it doesn’t effect on reactor power and neutron flux because the VVER-1200 nuclear power reactor has several safety features which undertake the situation and as a result, reactor trip did not happen. The data obtained from the simulation are satisfactorily consistent with PSAR (Preliminary Safety Assessment Report) data regarding SGTR accident. These findings are expected to provide useful information in understanding and evaluating plants capability to mitigate the consequence of SGTR accident.