Effect of Spray System on Fission Products Distribution in Containment during a Severe Accident in a Two-Loop Pressurized Water Reactor

Effect of Spray System on Fission Products Distribution in Containment during a Severe Accident in a Two-Loop Pressurized Water Reactor

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 is considered 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 of the influence of spray on retention of fission products and prevention of hydrogen combustion in containment.

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 is considered 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 of the influence of spray on retention of fission products and prevention of hydrogen combustion in containment.