CALCULATION OF THE ACTIVITY OF AN URANIUM SAMPLE IRRADIATED BY THERMAL NEUTRONS FOR THE INITIAL ANALYSIS IN RADIOLOGICAL PROTECTION USING MONTE CARLO SIMULATION

Abstract

To carry out the analysis of radiological protection and degree of danger of a practice in a facility that uses ionizing radiation, an analysis is made from computational calculations, both of gamma and neutron radiation, which are those of greater reach and penetration. The objective is to determine the dose produced by the interaction of these radiations with matter at the different points of a facility for a practice of interest consisting in irradiating a gram of uranium dioxide in a neutron flux of 1011 n cm2 s-1 for 40 s.

Keywords

• Neutrones
• Protección radiológica
• Uranio