The diploma thesis contains comparison of the simulation results small break loss of coolant accident with Advanced PWR simulator software and the results made by Westinghouse in the test facility APEX-1000.
The first part of the diploma thesis contains description of the primary and secondary system, which do not differ significantly from the systems of other nuclear power plants. This is followed by a description of the passive safety systems under which the AP1000 is known. Below, there is a general description of loss of coolant accident, Advanced PWR simulator software and conduct simulation. The last part presents the results of simulations, their comparison and comment.
The results show that the simulation tool Advanced PWR simulator is not suitable for a more detailed analysis of design accidents in nuclear power plants but can serve mainly as a tool to improve the understanding of the performance operation of the systems in nuclear power plants.
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