In the ongoing research, the Monte Carlo simulation of three different Barite Concrete samples coded as C-B0, C-B50 and C-B100 was estimated via MCNPX Monte Carlo Code to investigate the neutron-gamma photon shielding characteristics. Simulations were performed for Cf-252 source which is surrounded by the polyethylene cylinder. Using Watt Fission (WF) distribution and Doppler Effect (DE), the neutron-gamma photon flux was obtained and was compared to various types of Barite Concrete samples. The total macroscopic cross section, linear attenuation coefficient (mu), Half Value Thickness (HVT) and Mean Free Path (MFP) were calculated for gamma rays and neutrons. The equivalent absorbed dose rate was estimated for neutrons and showed that an increment of the Barite rate causes a reduction in the equivalent absorbed dose rate from 0.0003572 to 0.0003542 (mu SV/h). Moreover, total macroscopic cross section which shows total macroscopic cross section which shows the neutron attenuation coefficient ( n-ary sumation (t)) undergoes descending trend of ( n-ary sumation (t))(C-B0) < ( n-ary sumation (t))(C-B50) < ( n-ary sumation (t))(C-B100) which confirms the disability of the Barite Concrete sample against neutrons. The evaluated gamma photon attenuation parameters for energy ranging from 0.05 to 11 MeV are shown graphically. Findings reveal that by increasing the rate of the Barite, the samples' shielding ability will reduce against neutron whereas it will enhance the gamma photons shielding capability.