Estudio del comportamiento de un reactor nuclear pwr de 1gwe bajo la acción de las barras de control

Abstract

This study analyzes the dynamic behavior of a 1 GWe PWR nuclear reactor under the action of control rods, evaluating neutron variables such as reactivity and period, and thermohydraulic variables such as fuel and moderator temperature and power, using IAEA simulation software in six representative cases that include full power and zero-power conditions, power maneuvers, and burn-up cycles between 0 and 10 GWd/t. From the simulated transients, the reactivity-period-power-temperature feedback chain was identified, modulated by the neutron weight of the fuel banks, their movement speed, and the fuel burn-up, showing that heavy fuel banks generate greater parametric variability while light fuel banks exhibit greater neutron inertia. In addition, quasi-static and dynamic period models were implemented, as well as a simplified axial power model, which, despite the limitations of point kinetics and the homogeneous core, are useful as control tools, together establishing a methodological basis for describing the dynamics of the control banks and paving the way for the development of more complete predictive models in the design of power reactors