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Advances in Materials Research Volume 2, Number 2, June 2013 , pages 93-98 DOI: https://doi.org/10.12989/amr.2013.2.2.093 |
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Calculation of gamma buildup factors for point sources |
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Abouzar Kiyani, Abbas Ali Karami, Marziye Bahiraee and Hossein Moghadamian
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| Abstract | ||
| Objective of this study is to calculate gamma buildup factors for pointed and isotropic gamma sources in depleted uranium, uranium dioxide, natural uranium, tin, water and concrete using MCNP4C code. The thickness of the media ranges from 0.5 to 10 mean-free-path (mfp) and gamma energy ranges from 0.5 to 10 MeV. Owing to the outstanding accuracy of MCNP in calculation involving gamma interaction, results fairly match those reported previously. The maximum relative error is 2%. | ||
| Key Words | ||
| MCNP code; radiation shielding; buildup factors; mean free path; gamma | ||
| Address | ||
| Abouzar Kiyani :Payam Noor University, Nahavand, Iran Abbas Ali Karami: Bu-Ali Sina University, Department of Physics, Hamedan, Iran Marziye Bahiraee: Payam Noor University, Nahavand, Iran Hossein Moghadamian: Applied Sciences University, Islamshahr Branch, Iran | ||
