Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (7): 95 doi: 10.1007/s41365-017-0253-4

• LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS • Previous Articles     Next Articles

Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code

Huseyin Ozan Tekin1,2, Tugba Manici2

  1. 1 Vocational School of Health Service, Radiotherapy Department, Uskudar University, 34672 Istanbul, Turkey
    2 Medical Radiation Research Center (USMERA), Uskudar University, 34672 Istanbul, Turkey
  • Contact: Huseyin Ozan Tekin
Huseyin Ozan Tekin, Tugba Manici. Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code.Nuclear Science and Techniques, 2017, 28(7): 95     doi: 10.1007/s41365-017-0253-4


In this paper, mass attenuation coefficients of concrete, bricks and cement plaster, as shielding materials, are calculated at 59.5, 356, 662, 1173, 1274 and 1333 keV by using the MCNP-X (version 2.4.0) code. The numerical simulation results are compared with previous Monte Carlo studies, experimental results and XCOM data. The effects of barite on mass attenuation coefficients are investigated. The mass attenuation coefficients increase with the barite content. Thus, our results agree well with experimental studies on gamma ray shielding of barite. It is flexible for the MN method to change the barite rates in material by small increments, which is experimentally difficult. Also, modeled geometry can be used for future approaches such as new designs and new structures especially in investigating
new barite-containing materials to build nuclear reactors or high-energy radiation therapy facilities.

Key words: Monte Carlo simulation, Gamma ray attenuation, Barite (BaSO4)