پديدآورندگان :
Dehjourian Mehdi Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University,Tehran, Iran , Rahgoshay Mohammad Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University,Tehran, Iran , Sayareh Reza Faculty Electrical and Computer Engineering and Kerman Graduate University of Technology kerman Iran , Jahanfarnia Gholamreza Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University,Tehran, Iran , Shirani Amir Saied Faculty of Engineering, Shahid Beheshti University, Tehran, Iran Faculty of Engineering, Shahid Beheshti University, Tehran, Iran
كليدواژه :
CONTAIN , Loss , of , Coolant Accident , Pressurized Water Reactor , RELAP5 , SCDAP , Severe Accident
چكيده فارسي :
Th e 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. Th e accident considered in this study is a large-break loss-of-coolant accident, which is not successfully mitigated by the action of safety systems. Th e 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.
