Study and lmplementation of Neutronic-Thermohydraulic Coupling Methods for Detailed Analysis of Transients in Nuclear Reactors for Safety Margins Optimization

Abstract

Understanding the performance of a nuclear reactor is a complex task that covers different physical fields as the neutron behavior or fluid dynamics. These fields are not isolated, and there is a feedback among them. Along nuclear engineering history, different codes have been developed to analyze each of the physics in which the problem can be split in an isolated way. An example of this are the neutronic or the thermal-hydraulic codes. To study the performance of the reactor in a realistic way, it is necessary to take into account the interaction among the physics, or in other words, the codes have to be coupled. xiii ha facilitado en todo lo posible que pudiera seguir con mis estudios. Además, mis compañeros, Jorge, Paloma, Alfonso, Rosario, Carmen, Lustolde, David y Ruben se han asegurado de que acabara y me han hecho pasar buenos ratos, con unos buenos partidos y con frases como: "le vamos a decir a Edith que te quite el wifi" o "mucho ves tú Juego de Tronos".