Main steam line break analysis in 2775 MWth PWR reactor core

الملخص EN

This study aims to analyze the effects of accident of Main Steam Line Break (MSLB) for a three-loop Reactor, 2775 MWth PWR, where it can cause potential reactivity insertion accidents (RIA).

Multi-group diffusion depletion 3D code TRITON was used to calculate both the neutron flux and the power density distributions, depending on the cross sections at the beginning of cycle conditions, in the normal case, and in case of temperature decrease as a result of this accident.

The thermal-hydraulic calculations were carried out using a MATLAB script written to fit the power density values and to calculate the coolant temperature distribution inside the core.