Evaluation of Containment Failure and Fission Products Release during PWR Power Plant (BEZNAU) LOCA Severe Accident by MELCOR Code

Evaluation of Containment Failure and Fission Products Release during PWR Power Plant (BEZNAU) LOCA Severe Accident by MELCOR Code

The aim of the present work is to provide the evolution of the severe accident that can be expected during the LOCA in a two-loop PWR and the insights gained from the analysis. The MELCOR 1.8.6 is used to assess core degradation and the containment behavior during the large break loss-of-coolant (LBLOCA) without actuation of safety injection system (SIS). The predictions of the temperature and mass flow rates of water, steam, and hydrogen from the RCS and RPV failure time used to evaluation the failure time of containment. Besides possibility of hydrogen combustion and amount of fission products in the containment is investigated.

The aim of the present work is to provide the evolution of the severe accident that can be expected during the LOCA in a two-loop PWR and the insights gained from the analysis. The MELCOR 1.8.6 is used to assess core degradation and the containment behavior during the large break loss-of-coolant (LBLOCA) without actuation of safety injection system (SIS). The predictions of the temperature and mass flow rates of water, steam, and hydrogen from the RCS and RPV failure time used to evaluation the failure time of containment. Besides possibility of hydrogen combustion and amount of fission products in the containment is investigated.