Calculation of gamma buildup factors for point sources

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%.

[1]  S. M. Sadat kiai,et al.  Measurements of the Thermal Neutron Macroscopic Absorption Cross Section for Neutron Absorbing Layers , 2011 .

[2]  A. Abbaspour,et al.  Estimation of gamma- and X-ray photons buildup factor in soft tissue with Monte Carlo method. , 2009, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

[3]  Shirakawa.  A build-up treatment for thickness gauging of steel plates based on gamma-ray transmission , 2000, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

[4]  James E. Martin.  Physics for Radiation Protection , 2000 .

[5]  N. Tsoulfanidis,et al.  Exposure buildup factors of UO2 using the Monte Carlo method , 1996 .

[6]  S. Jiang,et al.  Gamma-Ray Buildup Factors for Stratified Lead and Water Shields , 1980 .