A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code

Half Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) coefficient. The purpose this study was to establish a direct computational model for determining HVL, vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. code's INPUT file designed with two detection locations primary secondary gamma-rays, as well attenuator between those detectors. Next, values some well-known materials such lead ordinary concrete have calculated throughout broad energy range. outcomes were then compared data from National Institute Standards Technology. obtained reported be highly compatible NIST standard database. Our results indicate that developed may utilized computations assessments medical applications. In conclusion, advanced simulation methods code are very powerful useful instruments should considered daily measures. input will provided scientific community upon reasonable request.