Nuclear power plants represent one of the key sources of electricity in modern energy systems, with Pressurized Water Reactors (PWR) being the most common reactor technology in use. Their operation is based on the nuclear fission of fuel, wherein heat from the primary loop transfers through steam generators to the secondary loop. The resulting steam in the secondary loop drives a turbine connected to an electrical generator, producing electricity.
This thesis examines the consequences of a main steam line break accident in a two-loop pressurized water reactor comparable to the Krško Nuclear Power Plant. The analysis was performed using the PCTRAN simulation software, enabling accurate modeling of plant operations and the response of safety systems. Two scenarios involving steam line breaks of 200 cm² and 300 cm² openings on one cooling loop were studied.
Simulation results indicate that, in both scenarios, key safety systems, such as automatic reactor shutdown (SCRAM) and high-pressure injection system (HPIS), activate rapidly. These systems effectively prevent reactor core overheating and maintain system parameters within acceptable safety limits.
The findings contribute to a better understanding of the dynamic response of a nuclear plant under such accident conditions and emphasize the importance of reliable safety systems for ensuring nuclear safety.
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