The few-group data library generation for a VVER-1200 core using the Monte Carlo code Serpent

This article presents the results of a comprehensive investigation focused on developing and validating a methodology for creating two-group cross-section libraries for the DYN3D reactor code in the formula format (IWQS = 2), utilizing the high-precision Monte Carlo code Serpent. The study specifically targets the VVER-1200 nuclear reactor at the Belarusian Nuclear Power Plant. The methodology involves calculating two-group cross-sections and other constants for various reactor states. It is demonstrated that the largest deviation for k_∞ for all types of fuel assemblies when calculated using the DYN3D code with the obtained library differs from precise Monte Carlo Serpent calculations by approximately 1000 ppm. This level of precision is deemed sufficient for safety analysis calculations using this library for the VVER-1200 reactor. Calculations of boric acid concentrations during the reactor’s first and stationary fuel cycles were performed, along with the distribution of energy release at the beginning of the campaign. The obtained results underscore the reliability and effectiveness of the developed methodology.

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