Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1739838 | Nuclear Engineering and Technology | 2016 | 7 Pages |
Abstract
The containment response during the first 24 hours of a low-pressure severe accident scenario in a nuclear power plant with a two-loop Westinghouse-type pressurized water reactor was simulated with the CONTAIN 2.0 computer code. The accident considered in this study is a large-break loss-of-coolant accident, which is not successfully mitigated by the action of safety systems. The analysis includes pressure and temperature responses, as well as investigation into the influence of spray on the retention of fission products and the prevention of hydrogen combustion in the containment.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Mehdi Dehjourian, Mohammad Rahgoshay, Reza Sayareh, Gholamreza Jahanfarnia, Amir Saied Shirani,