A transportable neutron radiography system

Fantidis, J. G.; Nicolaou, G. E.; Tsagas, N. F.
May 2010
Journal of Radioanalytical & Nuclear Chemistry;May2010, Vol. 284 Issue 2, p479
Academic Journal
A transportable neutron radiography system, incorporating a 50 mg 252Cf source, has been simulated using the MCNPX code. The materials considered were compatible with the European Union Directive on ‘Restriction of Hazardous Substances’ (RoHS) 2002/95/EC, hence excluding the use of cadmium and lead. The design was optimized with respect to neutron moderation, shielding and collimation. High density polyethylene was chosen as the material for moderator and also shielding, which was further enhanced with layers of bismuth and borated polyethylene. Variable values for the collimator ratio were calculated. With suitable aperture and collimator design it was possible to optimize the neutron radiography parameters. Beam filters also were treated in order to improve the results. The proposed system has been considered with a wide range of radiography parameters, which are comparable with neutron radiography facilities from low power reactors.


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