Abstract :
Background: Monte Carlo simulaons play a vital role in the calculaon of the
necessary shielding both for neutrons and photons. Advanced and simple
shielding materials against neutron and gamma rays were compared by
simulaon using the MCNB4B Monte Carlo code. The simulaons were
carried out for the three common neutron sources, namely the 252Cf, the
241Am/Be and the DD neutron generator which are suitable for transportable
facilies. Materials and Methods: The source has been simulated as sphere
with 3 cm diameter while the necessary shielding is designed in the form of a
sphere around the neutron source. The materials considered were chosen
according to the EU Direcve 2002/95/EC, hence excluding lead and
cadmium. Results: In the case of DD neutron generator the thickness, the
weight and the volume of the shield can decrease up to 41.3, 44, and 78.4%
correspondingly. With regard to the 252Cf neutron source the use of advanced
shielding materials can reduce the corresponding parameters up to 32.7,
40.7, and 68.4% respecvely. As regards the 241Am/Be neutron source, based
on advanced shielding materials the thickness, the mass and the volume of
the shield can decrease by 33.8, 49.5, and 70% respecvely. Conclusion: The
obtained results showed that the use of advanced shielding materials has led
to reduce greatly the weight and the volume of the necessary shield
