Collimator Design for Neutron Radiography Systems Using a Reactor Flux
نویسندگان
چکیده
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 n cm s by a collimator design set. 9 2 1
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