Modeling, verification and validation of multiple PWR depletion cycles with DRAGON and PARCS

This paper introduces a methodology for modeling Pressurized Water Reactors (PWRs) across multiple depletion cycles using the DRAGON and PARCS codes. The approach incorporates history effects to improve the accuracy of reactor simulations, specifically focusing on the evolution of PWR cores under irradiation. A succint, code-to-code verification of the history effect implementation is performed against the POLARIS/PARCS code system. Subsequently, simulations covering six depletion cycles in three distinct reactors—Fessenheim-2, Almaraz-2, and Turkey-Point-3—are evaluated against experimental data, including primary circuit boron concentration, axial offset, and neutron flux detector responses. The models demonstrate reasonable accuracy in comparison to measurements, highlighting their potential for testing and validating new nuclear data libraries, since all the steps, from ENDF-6 files to the calculations of core-follow parameters are included in the code system. • Modeling of PWR evolution across multiple cycles using DRAGON/PARCS. • Implementation of history effects in DRAGON/PARCS calculations. • Simulation of six cycles in Fessenheim-2, Almaraz-2, and Turkey-Point-3 reactors. • Accurate prediction boron letdown, neutron flux, and axial offset trends. • Supports nuclear data library testing from ENDF-6 to core-follow calculations.