Contributions to solve the Multi-group Neutron Transport equation with different Angular Approaches

Abstract

The most accurate way to know the movement of the neutrons through matter is achieved by solving the Neutron Transport Equation. Three different approaches to solve this equation have been investigated in this thesis: Discrete Ordinates Neutron Transport Equation, Neutron Diffusion Equation and Simplified Spherical Harmonics Equations.In order to solve the equations, different schemes of the Finite Differences Method were studied. The solution of these equations describes the population of neutrons and the occurred reactions inside a nuclear system. These variables are related with the flux and power, fundamental parameters for the Nuclear Safety Analysis.Por último, pero no menos importante, agradezco el apoyo de mi familia, mis hermanos y mi padre; y a los que me hacen sentir como tal, Jesús y Nati. Muy especialmente quiero dar las gracias a María, por estar siempre a mi lado e invitar a superarme. Finalmente, sería injusto no acordarme de mi madre a quien debo todo lo que soy.

Analysis of Core Configuration for Conceptual Gas Cooled Fast Reactor (Gfr) Using Openmc

“…At the reactor core, there is a neutron absorption reaction that causes the neutron population to decrease each time and the fission reaction which increases the population. These reactions need to control so the neutrons population in the reactor core could be maintained and the reactor could be operated [10,11].…”