Determination of Neutron Flux Viewed from the Maxwell-Boltzmann’s Statistical Distribution Using Numerical Approach

Abstract

Abstract This article aims to investigate the computational distribution of neutron flux using Maxwell-Boltzmann statistics. The reactor geometry used is a cylindrical shape. Identify the flux neutron only can when a neutron collides. Data analysis uses numerical analysis with the MATLAB 2013a program. The graph generated from a cylinder geometry is a histogram graph with the Poisson distribution by the Maxwell-Boltzmann distribution. There is a difference in the value of the neutron flux due to statistical uncertainty using a numerical approach. The purpose of writing this article is to determine the computational distribution of neutron fluxes in a cylindrical geometry reactor using Maxwell Boltzmann statistics. By writing this article it is hoped that it will become a reference material for further research or studies on computing the distribution of neutrons in other cases.