The Optimization of Material Thickness for Neutron Shielding with Monte Carlo Method

C. Chen; M. Wang

doi:10.4028/www.scientific.net/AMR.142.166

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HomeAdvanced Materials ResearchAdvanced Materials Research Vol. 142The Optimization of Material Thickness for Neutron...

The Optimization of Material Thickness for Neutron Shielding with Monte Carlo Method

Abstract:

Some materials are selected for shielding neutron radiation in this paper. The thickness of shielding materials is optimized with Monte Carlo method. The materials and optimizational thickness are: Tungsten 6cm, Polythene 8cm, Cadmium 1cm and Stainless Steel 1cm

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Periodical:

Advanced Materials Research (Volume 142)

Pages:

166-169

DOI:

https://doi.org/10.4028/www.scientific.net/AMR.142.166

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Online since:

October 2010

Authors:

C. Chen, M. Wang

Keywords:

Monte-Carlo Method (MC-Method), Neutron Radiation, Shielding Material

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References

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