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CÁLCULO DE LA ACTIVIDAD DE UNA MUESTRA DE URANIO IRRADIADA POR NEUTRONES TÉRMICOS PARA EL ANÁLISIS INICIAL EN PROTECCIÓN RADIOLÓGICA USANDO SIMULACIÓN MONTE CARLO
CALCULATION OF THE ACTIVITY OF AN URANIUM SAMPLE IRRADIATED BY THERMAL NEUTRONS FOR THE INITIAL ANALYSIS IN RADIOLOGICAL PROTECTION USING MONTE CARLO SIMULATION
Keywords:
Neutrones, Protección radiológica, Uranio (es)Neutrons, Radiological protection, Uranium (en)
Para efectuar el análisis de protección radiológica y grado de peligrosidad de una práctica en una instalación que utiliza radiación ionizante, se realiza un análisis proveniente de cálculos computacionales, tanto de radiación gamma como neutrónica, que son las de mayor de mayor alcance y penetración. El objetivo es determinar la dosis que produce la interacción de estas radiaciones con la materia en los diferentes puntos de una instalación para una práctica de interés consistente en irradiar un gramo de dióxido de uranio en un flujo neutrónico de 1011 n cm2 s-1 durante 40 s.
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.
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