Evaluation of Containment Failure and Fission Products Release during PWR Power Plant (BEZNAU) LOCA Severe Accident by MELCOR Code
Publish place: 4th International Conference on Reliability Engineering
Publish Year: 1395
نوع سند: مقاله کنفرانسی
زبان: English
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شناسه ملی سند علمی:
RELI04_103
تاریخ نمایه سازی: 1 مرداد 1397
Abstract:
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.
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Authors
Mehdi Dehjourian
Nuclear Engineering Department, Science and Research Branch, Islamic Azad University of Tehran, Tehran, Iran
Mohammad Rahgoshay
Nuclear Engineering Department, Science and Research Branch, Islamic Azad University of Tehran, Tehran, Iran