The current study is carried out to monitor radioactivity levels in Erediya younger granites of the Central Eastern Desert in Egypt by using a solid-state nuclear track detector (CR-39 NTD). The polymeric CR-39 NTD was used to determine radium-226 and radon-222 activity concentration, and the theoretical conversion equations, were employed to assess the radiological impact. Predetermined 33 samples were collected from different locations within and around Egypt's Eradia area fulfilling the IAEA TECDOC-1415 protocols. The measured overall average value of the radium and radon activity concentration are 7467.44±50.68 and 7840.14±53.2 Bqm -3 , respectively, which indicated a high abundance of TENORM in the collected samples of the investigated area. The exhalation rate and annual effective dose were calculated, indicating high grades than the permissible limit recommended by IAEA and UNSCEAR, and the average values are 0.87±0.01 Bqm -2 h -1 and 1637.82±26.87 mSvy -1 respectively. The present result is a reference for the radioactivity background as well as assesses any harmful radiation, and particularly helps in applying radiation protection principles for the occupational worker in the Erediya area. To furnish the outcome of the study, data was plotted as counter maps for tracking the distribution pattern of radioactivity levels and concerning radiation protection and human safety work level index was calculated to apply perfect radiation protection methodologies for the occupational.

A synthetic, ethylene-propylene-diene terpolymer monomer (EPDM) rubber reinforced with carbon-black (N-220) as a filler with the addition of different concentrations of lead powder (0-500 phr), was developed to be used as a radiation shielding against  -rays. Experimental studies on the influence of -radiation on the target samples were carried out using 137 CS (E  = 0.662 Mev) and ( 60 Co with energies of 1.172 Mev and 1.332 Mev). The attenuation coefficient and HVL were improved by two ways; one way by increasing the concentration of lead powder at constant thickness and the other by increasing the thickness of the composite samples at a constant concentration of lead powder. A high attenuation coefficient and HVL was obtained for 400phr lead (μ=0.0852 and 0.141 cm -1 for Eγ = 0.662, and 1.172 Mev respectively). Good results were also obtained for HVL when using 400phr lead (HVL= 8.137, 4.915, and 5.627 cm for Eγ = 0.662, 1.172, and 1.332 Mev respectively). For testing the moderating fast neutron emitted from 239 Pu-9 Be, samples containing 100, 200, and 300 phr lead and 25 phr borax were used. The results showed good enhancement/improvement in the values of the total macroscopic cross section. As a result of using the X.com program, it was found that the values of the linear and mass attenuation coefficients were in a good agreement with the experimentation values for uniform and collimated beams. However, this could not be confirmed for heterogeneous beams.