Collimator design for neutron radiography systems using a reactor flux

Abstract

This paper is aimed to investigate the design of an optimized neutron radiography system that utilizes the flux of a reactor. Moderation, collimation aspects are studied. A Monte Carlo code, MCNP4C, was utilized to achieve a maximum and more homogenous neutron flux in the collimator outlet next to the image plane, taking into account geometric characteristics. It was possible to obtain a normalized thermal neutron flux, at the image plane, equals 10-9n cm-2 s-1 by a collimator design set. © IDOSI Publications, 2012.