Simulación del comportamiento de un reactor nuclear PWR genérico de 2 bucles de 1GWe bajo pérdida transitoria del refrigerante

Abstract

This work analyses the behaviour of a 1 GWe pressurised water reactor (PWR) in the presence of a transient loss of coolant flow, using the Micro-Physics Nuclear Reactor Simulator Lite Edition simulator to evaluate the evolution of parameters such as power, reactivity, period, pressure, moderator density, fuel and coolant temperatures. A theoretical framework covering the concepts of neutrons, transport and diffusion as well as reactor thermohydraulics is developed, and the effects of fuel burn-up, cycle variation and initial power are analysed. The transient state of the reactor is modelled by an exponential dependence of the flux with a characteristic time of 2 seconds, and the results obtained over 10 seconds allow the comparison of different operating scenarios. The conclusions highlight the importance of these studies for understanding the safety and stability of nuclear reactors under adverse conditions, suggesting future work that delves deeper into thermohydraulics and the exploration of other transient events.