The comparison between simple and advanced shielding materials for the shield of portable neutron sources
International Journal of Radiation Research
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 252 Cf, the 241 Am/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
... 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 252 Cf 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 241 Am/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.